1BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

FISA2006 FISA2006 - LONG-TERM - LONG-TERM RESEARCH AND RESEARCH AND TRAINING FOR SUSTAINABLE DEVELOPMENT TRAINING FOR SUSTAINABLE DEVELOPMENT

IN THE NUCLEAR FIELD IN THE NUCLEAR FIELD FOUNDED BY THE FOUNDED BY THE EUROPEAN COMMISSIONEUROPEAN COMMISSION

ALNIKOLOV DPOPOV ALNIKOLOV DPOPOV

NPP KOZLODUYNPP KOZLODUY

2BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

ACKNOWLEDGEMENTS

Thanks tobull AssProf DrScEngIv Ivanov from Technical University of Sofia

- to have assured our attendance to FISArsquo06

bull Prof Aragones UPM Spain G LoumlwenhielmSKI Sweden T Shulenberg FZKGermany profB Bazargan-Sabet INPL-Ecole des Mines de Nancy France J-P Massoud EDF France D Warin CEA France J-Y Blanc CEA France M McDermott NNC Ltd GB W Raskob FZKGermany J-C Micaelli IRSN France JTuunanen TVO Finland

- to have sent personally their presentations in FISArsquo06

bull Mrs M Antoine secretary in Unit J4 DG RTD

- to have sent web links to FP-6

3BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

FISArsquo06 13-16 March Luxembourg

FISA=FIssion SAfety The FISA covers the entire spectrum of reactor safety research and trainingeducation in new nuclear fields that was included in last EURATOMrsquo Framework Program FP-6

Up to 350 participants of old and new EU countries and EU candidates but also from USA Switzerland Russia Ukraine Korea Japan Turkey and others not to mention international organisations such as IAEAOECDNEA

4BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

FISArsquo06 what expectations from

EC expected from FISA conference to improve the common vision on how to tackle the challenges of common interest in view of the upcoming critical deadline of 2010-2020 when many nuclear installations will have to be replacedhellip

hellipand also to examine the future nuclear alternatives

5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Energy needs of EU Community

EU25 Growth of import dependency

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo

FISArsquo06)

6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTS

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

KEEPING THE NUCLEAR OPTION OPEN

NEED FOR DRASTIC DECREASE OF THE CARBON INTENSITY IN THE ECONOMY

ADDRESSING THE CHALLENGES OF GLOBAL WARMING

EMPHASIS ON THE SAFETY OF INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY

EC Green Paper 8 March 2006

7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Features of Gen IV

1 High Safety Level

2 Good Economy

21 High efficiency (η~ up to 50)

22Possibility to develop H2 industry

3 Proliferation resistance (Minor Actinides)

EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts

Water-Cooled

1 Super-Critical Water Reactor (SCWR)

Gas-cooled

2Very-High Temperature Reactor (VHTR)

3Gas-cooled Fast Reactor (GCFR)

Liquid Metal-Cooled

4 Sodium cooled Fast Reactor (SFR)

5 Lead Fast Reactor (LFR) Pb-Bi cooled

Non-Classical

6 Molten Salt cooled Reactor (MSR)

6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT

(~2030)

8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor

FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to

bull deliver Electricitybull deliver Hydrogen

From breeder to burner and recycling minor actinides

closed fuel cycle for efficient conversion of fertile uranium and management of actinides

Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant

Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

2BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

ACKNOWLEDGEMENTS

Thanks tobull AssProf DrScEngIv Ivanov from Technical University of Sofia

- to have assured our attendance to FISArsquo06

bull Prof Aragones UPM Spain G LoumlwenhielmSKI Sweden T Shulenberg FZKGermany profB Bazargan-Sabet INPL-Ecole des Mines de Nancy France J-P Massoud EDF France D Warin CEA France J-Y Blanc CEA France M McDermott NNC Ltd GB W Raskob FZKGermany J-C Micaelli IRSN France JTuunanen TVO Finland

- to have sent personally their presentations in FISArsquo06

bull Mrs M Antoine secretary in Unit J4 DG RTD

- to have sent web links to FP-6

3BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

FISArsquo06 13-16 March Luxembourg

FISA=FIssion SAfety The FISA covers the entire spectrum of reactor safety research and trainingeducation in new nuclear fields that was included in last EURATOMrsquo Framework Program FP-6

Up to 350 participants of old and new EU countries and EU candidates but also from USA Switzerland Russia Ukraine Korea Japan Turkey and others not to mention international organisations such as IAEAOECDNEA

4BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

FISArsquo06 what expectations from

EC expected from FISA conference to improve the common vision on how to tackle the challenges of common interest in view of the upcoming critical deadline of 2010-2020 when many nuclear installations will have to be replacedhellip

hellipand also to examine the future nuclear alternatives

5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Energy needs of EU Community

EU25 Growth of import dependency

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo

FISArsquo06)

6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTS

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

KEEPING THE NUCLEAR OPTION OPEN

NEED FOR DRASTIC DECREASE OF THE CARBON INTENSITY IN THE ECONOMY

ADDRESSING THE CHALLENGES OF GLOBAL WARMING

EMPHASIS ON THE SAFETY OF INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY

EC Green Paper 8 March 2006

7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Features of Gen IV

1 High Safety Level

2 Good Economy

21 High efficiency (η~ up to 50)

22Possibility to develop H2 industry

3 Proliferation resistance (Minor Actinides)

EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts

Water-Cooled

1 Super-Critical Water Reactor (SCWR)

Gas-cooled

2Very-High Temperature Reactor (VHTR)

3Gas-cooled Fast Reactor (GCFR)

Liquid Metal-Cooled

4 Sodium cooled Fast Reactor (SFR)

5 Lead Fast Reactor (LFR) Pb-Bi cooled

Non-Classical

6 Molten Salt cooled Reactor (MSR)

6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT

(~2030)

8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor

FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to

bull deliver Electricitybull deliver Hydrogen

From breeder to burner and recycling minor actinides

closed fuel cycle for efficient conversion of fertile uranium and management of actinides

Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant

Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

3BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

FISArsquo06 13-16 March Luxembourg

FISA=FIssion SAfety The FISA covers the entire spectrum of reactor safety research and trainingeducation in new nuclear fields that was included in last EURATOMrsquo Framework Program FP-6

Up to 350 participants of old and new EU countries and EU candidates but also from USA Switzerland Russia Ukraine Korea Japan Turkey and others not to mention international organisations such as IAEAOECDNEA

4BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

FISArsquo06 what expectations from

EC expected from FISA conference to improve the common vision on how to tackle the challenges of common interest in view of the upcoming critical deadline of 2010-2020 when many nuclear installations will have to be replacedhellip

hellipand also to examine the future nuclear alternatives

5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Energy needs of EU Community

EU25 Growth of import dependency

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo

FISArsquo06)

6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTS

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

KEEPING THE NUCLEAR OPTION OPEN

NEED FOR DRASTIC DECREASE OF THE CARBON INTENSITY IN THE ECONOMY

ADDRESSING THE CHALLENGES OF GLOBAL WARMING

EMPHASIS ON THE SAFETY OF INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY

EC Green Paper 8 March 2006

7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Features of Gen IV

1 High Safety Level

2 Good Economy

21 High efficiency (η~ up to 50)

22Possibility to develop H2 industry

3 Proliferation resistance (Minor Actinides)

EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts

Water-Cooled

1 Super-Critical Water Reactor (SCWR)

Gas-cooled

2Very-High Temperature Reactor (VHTR)

3Gas-cooled Fast Reactor (GCFR)

Liquid Metal-Cooled

4 Sodium cooled Fast Reactor (SFR)

5 Lead Fast Reactor (LFR) Pb-Bi cooled

Non-Classical

6 Molten Salt cooled Reactor (MSR)

6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT

(~2030)

8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor

FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to

bull deliver Electricitybull deliver Hydrogen

From breeder to burner and recycling minor actinides

closed fuel cycle for efficient conversion of fertile uranium and management of actinides

Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant

Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

4BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

FISArsquo06 what expectations from

EC expected from FISA conference to improve the common vision on how to tackle the challenges of common interest in view of the upcoming critical deadline of 2010-2020 when many nuclear installations will have to be replacedhellip

hellipand also to examine the future nuclear alternatives

5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Energy needs of EU Community

EU25 Growth of import dependency

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo

FISArsquo06)

6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTS

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

KEEPING THE NUCLEAR OPTION OPEN

NEED FOR DRASTIC DECREASE OF THE CARBON INTENSITY IN THE ECONOMY

ADDRESSING THE CHALLENGES OF GLOBAL WARMING

EMPHASIS ON THE SAFETY OF INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY

EC Green Paper 8 March 2006

7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Features of Gen IV

1 High Safety Level

2 Good Economy

21 High efficiency (η~ up to 50)

22Possibility to develop H2 industry

3 Proliferation resistance (Minor Actinides)

EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts

Water-Cooled

1 Super-Critical Water Reactor (SCWR)

Gas-cooled

2Very-High Temperature Reactor (VHTR)

3Gas-cooled Fast Reactor (GCFR)

Liquid Metal-Cooled

4 Sodium cooled Fast Reactor (SFR)

5 Lead Fast Reactor (LFR) Pb-Bi cooled

Non-Classical

6 Molten Salt cooled Reactor (MSR)

6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT

(~2030)

8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor

FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to

bull deliver Electricitybull deliver Hydrogen

From breeder to burner and recycling minor actinides

closed fuel cycle for efficient conversion of fertile uranium and management of actinides

Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant

Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

5BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Energy needs of EU Community

EU25 Growth of import dependency

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

U3O8 spot prices since 1990(Source TAbram ldquoIntegration of niternational research in innovative GenIV system rdquo

FISArsquo06)

6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTS

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

KEEPING THE NUCLEAR OPTION OPEN

NEED FOR DRASTIC DECREASE OF THE CARBON INTENSITY IN THE ECONOMY

ADDRESSING THE CHALLENGES OF GLOBAL WARMING

EMPHASIS ON THE SAFETY OF INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY

EC Green Paper 8 March 2006

7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Features of Gen IV

1 High Safety Level

2 Good Economy

21 High efficiency (η~ up to 50)

22Possibility to develop H2 industry

3 Proliferation resistance (Minor Actinides)

EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts

Water-Cooled

1 Super-Critical Water Reactor (SCWR)

Gas-cooled

2Very-High Temperature Reactor (VHTR)

3Gas-cooled Fast Reactor (GCFR)

Liquid Metal-Cooled

4 Sodium cooled Fast Reactor (SFR)

5 Lead Fast Reactor (LFR) Pb-Bi cooled

Non-Classical

6 Molten Salt cooled Reactor (MSR)

6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT

(~2030)

8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor

FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to

bull deliver Electricitybull deliver Hydrogen

From breeder to burner and recycling minor actinides

closed fuel cycle for efficient conversion of fertile uranium and management of actinides

Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant

Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

6BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTS

Source J Mišaacutek F Pazdera ldquoFuture prospects for European cooperation in nuclear safety researchrdquoFISArsquo06

KEEPING THE NUCLEAR OPTION OPEN

NEED FOR DRASTIC DECREASE OF THE CARBON INTENSITY IN THE ECONOMY

ADDRESSING THE CHALLENGES OF GLOBAL WARMING

EMPHASIS ON THE SAFETY OF INSTALLATIONS AND OF DISTRIBUTION NETWORKS AND SECURITY OF SUPPLY

EC Green Paper 8 March 2006

7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Features of Gen IV

1 High Safety Level

2 Good Economy

21 High efficiency (η~ up to 50)

22Possibility to develop H2 industry

3 Proliferation resistance (Minor Actinides)

EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts

Water-Cooled

1 Super-Critical Water Reactor (SCWR)

Gas-cooled

2Very-High Temperature Reactor (VHTR)

3Gas-cooled Fast Reactor (GCFR)

Liquid Metal-Cooled

4 Sodium cooled Fast Reactor (SFR)

5 Lead Fast Reactor (LFR) Pb-Bi cooled

Non-Classical

6 Molten Salt cooled Reactor (MSR)

6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT

(~2030)

8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor

FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to

bull deliver Electricitybull deliver Hydrogen

From breeder to burner and recycling minor actinides

closed fuel cycle for efficient conversion of fertile uranium and management of actinides

Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant

Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

7BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Features of Gen IV

1 High Safety Level

2 Good Economy

21 High efficiency (η~ up to 50)

22Possibility to develop H2 industry

3 Proliferation resistance (Minor Actinides)

EURATOM FP-6 PROJECTSGeneration-IV Innovative Concepts

Water-Cooled

1 Super-Critical Water Reactor (SCWR)

Gas-cooled

2Very-High Temperature Reactor (VHTR)

3Gas-cooled Fast Reactor (GCFR)

Liquid Metal-Cooled

4 Sodium cooled Fast Reactor (SFR)

5 Lead Fast Reactor (LFR) Pb-Bi cooled

Non-Classical

6 Molten Salt cooled Reactor (MSR)

6 REACTOR SYSTEMS SELECTED BY GIF FOR FURTHER DEVELOPMENT

(~2030)

8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor

FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to

bull deliver Electricitybull deliver Hydrogen

From breeder to burner and recycling minor actinides

closed fuel cycle for efficient conversion of fertile uranium and management of actinides

Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant

Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

8BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor

FEATURES Lead-cooled by natural convection Outlet temperature of the helium 850 C Possible to

bull deliver Electricitybull deliver Hydrogen

From breeder to burner and recycling minor actinides

closed fuel cycle for efficient conversion of fertile uranium and management of actinides

Reference reactor - 600-MWth288-MWe using a direct Brayton cycle gas turbine for high thermal efficiency The GCFR reference has an integrated on-site spent fuel treatment and refabrication plant

Through the combination of a fast spectrum and full recycle of actinides the GCFR minimizes the production of long-lived radioactive waste

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

9BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndashcontrsquod

Fuel type CERCER plate fuel - hold the potential to operate at very high temperatures and to ensure an excellent retention of fission products

bullcomposite ceramic fuel bulladvanced fuel particles or bullceramic clad elements of actinide compounds

Core configurations may be based on prismatic blocks pin- or plate-based assemblies (TUD)

PARTICIPANTS

National Nuclear Corporation Ltd NNC

Nexia Solutions NEXIA

Commissariat agrave lrsquoEnergie Atomique CEA

Empresarios Agrupados Internacional SA EA

Framatome ANP SAS FANP SAS

Joint Research Centre ndash ITU and IE JRC

Nuclear Research and Consultancy Group NRG

Paul Scherrer Institut PSI

Delft University of Technology TUD

InterUniversities Consortium for Nuclear Technological Research ndash University of Pisa

CIRTEN-UNIPI

The GFR system is top-ranked in sustainability because of its closed fuel cycle and excellent

performance in actinide management It is rated good in

safety economics and in proliferation resistance and

physical protectionCERCER plate fuel High power density ~ 100 MWm^3

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

10BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsGas Cooled Fast Reactor ndash contrsquod

Development Strategy

Commercial electricity production plant bull GFR 2400 MWth (modular 600 MWth) by ~2030

ETDR (Experimental Technology Demonstrator Reactor)bull 20-50 MWth first GCFR at Cadarache Francebull Separate project from 2008 decision to build 2012bull Contrasts earlier GCFR projects (direct to

prototypedemo)Synergies with HTR

bull Helium-gas cooledbull High temperature materials and components

ndash Benefit from FP6 RAPHAEL-IPGen IV VHTR

750

00

195

00

01

200

689

14436

656

25

990

00

120

000

2650

4700

15500

689

250

000

7000

640

00

673827

908

00

0

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

11BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System

FEATURES

Lead-cooled by natural convection fast-neutron spectrum Fuel = MOX

Outlet temperature of the helium 550 C up to 850 C depending on the advanced materials to be used

Possible to

bull deliver Electricity

bull deliver Hydrogen

bull deliver potable Water

Full actinide recycle fuel cycle with central or regional fuel cycle facilities

Options include a range of plant ratings including a battery of 50-150 MWe that features a very long refueling interval (15-20 yr) with cassette core or replaceable reactor module a modular system rated at 300-400 MWe and a large monolithic plant option at 1200

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

12BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsLCR - Lead Cooled (Fast) Reactor System ndash contrsquod

Sustainability- Resource utilization Because lead is a coolant with very low neutron absorption and moderation it makes possible an efficient utilization of excess neutrons and reduction of specific uranium consumption Reactor designs can readily achieve a breeding ratio of about 1 and long core life and a high fuel burnup can be achieved-Waste minimization and management A fast neutron flux significantly reduces waste generation Pu recycling in a closed cycle being the condition recognized by GEN IV for waste minimization The capability of the LFR systems to safely burn recycled minor actinides within the fuel will add to the attractiveness of the LFREconomics-Life cycle cost The cost advantage features of the LFR must include low capital cost short construction duration and low fuel and low production cost The economic utilization of MOX fuel in a fast spectrum has been already demonstrated in the case of the SFR and no significantly different conclusion can be expected for the LFR except from improvement due to the harder spectrum

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

13BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Because of the favorable characteristics of molten lead it will be possible to significantly simplify the LFR systems in comparison with the well known designs of the SFRs and hence to reduce its overnight capital cost which is a major cost factor for the competitive generation of nuclear electricityA simple plant will be the basis for reduced capital and operating cost A pool-type low-pressure primary system configuration offers great potential for plant simplification

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

14BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SFR ndash Sodium-Cooled Fast Reactor System

The Sodium-Cooled Fast Reactor (SFR) system features fast-neutron spectrum and a closed fuel cycle for efficient conversion of fertile uranium and management of actinides A full actinide recycle fuel cycle is envisioned with two major options One is an intermediate size (150 to 500 MWe) sodium-cooled reactor with uranium-plutonium-minor-actinide-zirconium metal alloy fuel supported by a fuel cycle based on pyrometallurgical processing in collocated facilities The second is a medium to large (500 to 1500 MWe) sodium-cooled fast reactor with mixed uranium-plutonium oxide fuel supported by a fuel cycle based upon advanced aqueous processing at a central location serving a number of reactors The outlet temperature is approximately 550degCfor both The primary focus of the RampD is on the recycle technology economics of the overall system assurance of passive safety and accommodation of bounding events

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCR - Sodium-Cooled (Fast) Reactor System

The SFR system is top-ranked in sustainability becauseof its closed fuel cycle and excellent

potential foractinide management including resource extension It israted good in safety economics and proliferationresistance and physical protection It is

primarilyenvisioned for missions in electricity production andactinide management The SFR system is the nearesttermactinide management

system Based on the experiencewith oxide fuel this option is estimated to bedeployable by 2015

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

15BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsSCWR ndash Supercritical-Water-Cooled Reactor System

The Supercritical-Water-Cooled Reactor (SCWR )system features two fuel cycle options the first is an open cycle with a thermal neutron spectrum reactor the second is a closed cycle with a fast-neutron spectrum reactor and full actinide recycle Both options use a high-temperature high-pressure water-cooled reactor that operates above the thermodynamic critical point of water (221 MPa 374degC) to achieve a thermal efficiency approaching 44 The fuel cycle for the thermal option is a once-through uranium cycle The fast-spectrum option uses central fuel cycle facilities based on advanced aqueous processing for actinide recycle The fast-spectrum option depends upon the materialsrsquo RampD success to support a fast-spectrum reactor

In either option the reference plant has a 1700-MWepower level an operating pressure of 25 MPa and reactor outlet temperature of 550degC Passive safety features similar to those of the simplified boiling water reactor are incorporated Owing to the low density of supercritical water additional moderator is added to thermalize the core in the thermal option Note that the balance-of-plant is considerably simplified because the coolant does not change phase in the reactor

The SCWR system is highly ranked in economics because of the high thermal efficiency and plant simplification If the fast-spectrum option can be developed the SCWR system will also be highly ranked in sustainability The SCWR is rated good in safety and in proliferation resistance and physical protection The SCWR system is primarily envisioned for missions in electricity production with an option for actinide management Given its RampD needs in materials compatibility the SCWR system is estimated to be deployable by 2025

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

16BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsVHTR ndash Very-High-Temperature Reactor System

The Very-High-Temperature Reactor (VHTR) system uses a thermal neutron spectrum and a once-through uranium cycle The VHTR system is primarily aimed at relatively faster deployment of a system for high temperature process heat applications such as coal gasification and thermochemical hydrogen production with superior efficiency

The reference reactor concept has a 600-MWth helium cooled core based on either the prismatic block fuel of the Gas TurbinendashModular Helium Reactor (GT-MHR) or the pebble fuel of the Pebble Bed Modular Reactor (PBMR) The primary circuit is connected to a steam reformersteam generator to deliver process heat The VHTR system has coolant outlet temperatures above 1000degC It is intended to be a high-efficiency system that can supply process heat to a broad spectrum of high temperature and energy-intensive nonelectric processes The system may incorporate electricity generation equipment to meet cogeneration needs The system also has the flexibility to adopt UPu fuel cycles and offer enhanced waste minimization The VHTR requires significant advances in fuel performance and high temperature materials but could benefit from many of the developments proposed for earlier prismatic or pebble bed gas-cooled reactors Additional technology RampD for the VHTR includes high-temperature alloys fiber-reinforced ceramics or composite materials and zirconium-carbide fuel coatings

The VHTR system is highly ranked in economics because of its high hydrogen production efficiency and in safety and reliability because of the inherent safety features of the fuel and reactor It is rated good in proliferation resistance and physical protection and neutral in sustainability because of its open fuel cycle It is primarily envisioned for missions in hydrogen production and other process-heat applications although it could produce electricity as well The VHTR system is the nearest-term hydrogen production system estimated to be deployable by 2020

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

17BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSGeneration-IV Innovative ConceptsMSR- Molten Salt Reactor Sytem

The Molten Salt Reactor (MSR) system produces fission power in a circulating molten salt fuel mixture with an epithermal-spectrum reactor and a full actinide recycle fuel cycle

In the MSR system the fuel is a circulating liquid mixture of sodium zirconium and uranium fluorides The molten salt fuel flows through graphite core channels producing an epithermal spectrum The heat generated in the molten salt is transferred to a secondary coolant system through an intermediate heat exchanger and then through a tertiary heat exchanger to the power conversion system The reference plant has a power level of 1000 MWe The system has a coolant outlet temperature of 700 degrees Celsius possibly ranging up to 800 degrees Celsius affording improved thermal efficiency

The closed fuel cycle can be tailored to the efficient burn up of plutonium and minor actinides The MSRs liquid fuel allows addition of actinides such as plutonium and avoids the need for fuel fabrication Actinides - and most fission products - form fluorinides in the liquid coolant Molten fluoride salts have excellent heat transfer characteristics and a very low vapor pressure which reduce stresses on the vessel and piping

The MSR system is top-ranked in sustainability because of its closed fuel cycle and excellent performance in waste burndown It is rated good in safety and in proliferation resistance and physical protection and it is rated neutral in economics because of its large number of subsystems It is primarily envisioned for missions in electricity production and waste burndown Given its RampD needs for system development the MSR is estimated to be deployable by 2025

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

18BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research

Information Database and Knowledge Management Links 25 PARTICIPANTS

HU AEKI VEIKI

CZ NRI CTU NSTC

SK VUJE STU CENS

FI FORTUM VTT LUT

EU JRC IE

DE GRS FZR

NL NRG

BG INRNE TUS ENIN REL

RU RRCKI OKBGP EREC

UA NPPOSI SSTCNRS ISTC

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

19BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

bullAssessing topics contributing to enhancement of VVER operational safety and reliabilitybullAssessing ldquogood practicesrdquo for the areas of nuclear safety and plant life managementbullCreating common database of VVER relevant data as well as the corresponding dissemination platformsbullIdentifying and initiating requisite RampD tasks ndashanalytical and experimental

bullStrengthening communication with OECD and IAEA programs especially those of experimental researchbullMaking use of information acquired within participation in other EURATOM FP6 projects integrating it for VVER purposes (SARNET NURESIM NEPTUNO PERFECT)bullStrengthening links between parties involved in VVER safety research and creating conditions for efficient exchange of information and cooperation even after the project is completed

Project Objectives

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

20BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP3 Operational Safety

Five task groups

Group A Basic VVER safety items Task Discussion identification and recommendations of the safety research needs

Group B Experimental facilities and code validationTask Information exchange in computer code validation

Group C Severe accident assessment and management Task Inventarisation of SAM-approaches and formulation of recommended approaches for VVER

Group D Safety of refuelling pools

Task Collection of activities in the field of spent fuel storage pool safety

Group E Steering activities in operational safety

In task group B a draft report was prepared Identification of the VVER experimental facilities and description of the available and missing experimental capabilities

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

21BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

WP3 Material and equipment ageing 4 subgroups RPV Steam generator Piping and other passive primary

components Fatigue Dosimetry

Upgrading and extending the VERLIFE code (PTS P-T diagram surveillance MasterCurve etc) and discussion of VERLIFE experience and upgrade

Collecting and exchanging new information on VVER Life Management practices (national solutions and practices)

Collecting new information on VVER material ageing and life performance (eg Irradiation effect on cladding application of Master Curve annealing steam generator corrosion etc)

Determining fields where new common research is required

Define further necessary (common) RampD and prepare common proposals

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP5 Training and good practices exchange 2005 Kick-off meetings 2006 Training meetingspreparation of the reports presentations for the End UsersAdvisory Group dissemination of knowledge for the invited participants (students docs young

specialists in nuclear) for all WPs

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

22BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSCOVERS ndash VVER Safety Research - contrsquod

WP2 Information database and knowledge managementWeb portal (GRS) Document management Rights management Collaboration (shared and meeting workspaces discussions events announcements) Search and retrieval PersonalizationUser training1048698User support and usage guidelines1048698Continuous introduction of content (Documents information links)1048698Extension of functionality according to specific requirements of the teams

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

23BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM SCOPE AND OBJECTIVES

Feb 2005 ndash Jan 2008

18 Organizations13 Countries

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulation

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

24BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

NURESIM PLATFORM

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

25BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks

SP1 CORE PHYSICS

WP11 Advanced Monte Carlo MethodsbullTRIPOLI4 (CEA) + Adjoin methods (TUD+KTH)

WP12 Advanced Deterministic Diffusion and Transport Methods

bullAPOLLO2 + CRONOS =gt DESCARTES (CEA)bullANDES nodal solver + COBAYA3 cell-nodal (UPM)

WP13 Advanced Neutron Kinetics MethodsbullDESCARTES + COBAYA3 + DYN3D (FZR)

WP14 Coupled Calculations and Transient Benchmarks (MSLB CRE for PWRVVER)

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

26BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP2 THERMALHYDRAULICS (with CFD)WP 21 Pressurized Thermal Shock amp Direct Contact CondensationWP 22 Critical Heat Flux

SCIENTIFIC CHALLENGES ASSOCIATED TO PTS and CHF

bull Condensation on the jetbull Bubble Entrainment by jetbull Turbulence production below jetbull Turbulence production at free surfacebull Turbulence effects on condensationbull Friction at free surface

bull Interactions betweenbull waves turbulence amp condensationbull Effects of Tdeg stratificationbull Flow Separationbull Wall to fluid in CL amp downcomer

bull Review of existing databull Identification of experimental needsbull Implementation of available modules bull Development of new physical modelsbull Benchmarking and assessment

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

27BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquod

SP3 MULTIPHYSICS

Review and specification within the NURESIM platform of coupling schemes for core analysis based on existing CP and TH core codes

bullAt the nodal level (fuel assembly)

bullAt the sub-node level (pin)

Development and integration within the NURESIM platform of core parameters interpolation and averaging schemes and data transfer

Application to PWR (MSLB) and BWR

A multi-scale analysis of accidental transients with 3D simulation

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

28BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

Structure amp Tasks ndash contrsquodSP4 SENSITIVITY AND UNCERTAINTY Sensitivity and uncertainty analysis of multiphysics modules

- State of the Art report on deterministic and statistical methods- Evaluation of critical points of model responses

Implementation within the NURESIM platform of procedures for propagation of uncertainties

SP5 INTEGRATIONbull Specific training courses on

the SALOME platformbull Assistance in integrating

codesbull Adaptation of the SALOME

platformbull Ensuring consistency and

non-regression

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

29BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

EURATOM FP-6 PROJECTSSAFETY OF EXISTING INSTALLATIONSNURESIM ndash European Platform for Nuclear Reactor Simulationndash contrsquod

bull NURESIM PROVIDES THE BASIS FOR A LONG TERM STRATEGY TOWARDS A EUROPEAN SOFTWARE PLATFORM FOR NUCLEAR ENERGY

bull STRONG POSSIBLE BREAKTHROUGHS IN PHYSICAL MODELLING NUMERICAL METHODS AND COMPUTER SCIENCE

bull UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR UNIFY EFFORTS IN NUMERICAL SIMULATION IN REACTOR APPLICATIONS INSTEAD OF DISPERSED ONES NOWAPPLICATIONS INSTEAD OF DISPERSED ONES NOW

bull AN ANSWER TO MEET THE NEEDS OF THE EUROPEAN NUCLEAR INDUSTRY TO MAINTAIN ITS EFFICIENCY AND COMPETITIVENESS

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention

30BULATOMBULATOM VARNAVARNA 02-04 June 02-04 June 20020066

SOME USEFUL WEB LINKS

bullhttp www cordiseuropaeufp6

bullhttp wwwnuresimorg

bullhttp wwweu-nerisnet

bullhttpiriaxpiritudelftnl

bullhttpgifinelgov

bullhttp wwwgcfrorg

Thank you for your attention