construction of research reactors for gen 3 & …...construction of research reactors for gen 3...
TRANSCRIPT
CONSTRUCTION OF RESEARCH
REACTORS FOR GEN 3 & GEN 4
REACTORS DEVELOPMENT
OCTOBER 13th, 2014
Atoms for the future | Christophe Béhar
| PAGE 1 Christophe Béhar | October 13, 2014
RESEARCH REACTORS:
USE AND HISTORY
| PAGE 2
Christophe Béhar | October 13, 2014
A KEY ROLE IN NUCLEAR ENERGY DEVELOPMENT
Research reactors have accompanied the development of nuclear
power since the beginning
On December 2, 1942 a team of scientists conducted by Enrico Fermi
succeeded in initiating the first controlled chain reaction and,
so, in operating the first experimental atomic pile in Chicago
From the 1945’s to date, more than 600 research reactors or critical assemblies were
built in the world, with powers ranging approximately from zero to several hundred thermal
megawatts, along with a high diversity in design, use and operating mode
In France, ~ 40 research reactors built since 1948 (ZOE), the last one (JHR) is under
construction in Cadarache
| PAGE 3
Evolution of the number of operating research reactors registered in the world
Enrico FERMI
Christophe Béhar | October 13, 2014
USE AND TYPOLOGY
Research Reactors are nuclear facilities in which a fission chain reaction is generated and
sustained so as to get a neutron flux to be used for experiments
Neutrons generated in research reactors are first used to achieve experiments related to the
development of nuclear power reactors, for both the understanding of the phenomena
involved, and as well as the validation and qualification of the retained solutions
3 main categories of Research Reactors have to be considered in relation to this issue :
Reactors designed to validate neutronics calculations of power reactors, also called
Zero Power Reactors (ZPRs), or sometimes “critical mockups”
Reactors designed to investigate and qualify the behavior of structural materials and
fuels under irradiation, also called Material Test Reactors (MTRs)
Reactors designed to investigate accidental situations, also called “Safety Test
Reactors”
In addition, Research Reactors can be used for:
producing radioelements for medicine
contributing to scientific research tools for investigating atomic and nuclear structures
of the matter, they are categorized as neutron beam (High Flux) Reactors
| PAGE 4 Christophe Béhar | October 13, 2014
| PAGE 5
SOME EXAMPLES
BR2 MTR Reactor (Belgium)
OSIRIS MTR Reactor
(France)
EOLE ZPR (France)
MINERVE ZPR
(France)
HFR High Flux Reactor
(ILL – France)
Christophe Béhar | October 13, 2014
RESEARCH REACTORS TODAY AND TOMORROW
Research Reactors are essential to pursue the development of present NPPs and prepare
the nuclear systems of the future, and this all the more as a technological disruption step
is considered
despite the boost of simulation (through High Performance Computing – HPC) , with
especially the widespread use of Monte-Carlo-type calculations, there remain fields where
experimentation is still indispensable:
model readjustment
validation of basic phenomena
description and qualification of technological objects (reactors, components, fuels)
Reduction of operational margins, improvement in Safety aspects and demonstration,
as well as design uncertainties
3 major CEA projects for the future:
From EOLE & MINERVE facilities to ZEPHYR, in complementarity with MASURCA :
experimental validation of codes, calculation schemes and associated nuclear DATA
MASURCA (ZPR) , currently being refurbished, for Gen-IV core physics
JHR, an innovative MTR
| PAGE 6 Christophe Béhar | October 13, 2014
FROM EOLE & MINERVE FACILITIES
TO ZEPHYR, COMPLEMENTARY WITH
MASURCA
| PAGE 7
Christophe Béhar | October 13, 2014
THE CONTEXT
All the major countries involved in the nuclear field developed critical facilities, but many
of them were shut down ; France made a different choice by maintaining its three most
multipurpose ZPRs in continuous operation for more than 40 years: EOLE, MINERVE
and MASURCA
The neutronics behavior of various configurations investigated in these ZPRs can be
directly extrapolated to the physical phenomena encountered in power reactors, by
allowing for a representativeness factor. While being safe, these mockups are highly
flexible, adaptable, easily accessible, and easy to instrument
The so-called Integral experiments performed therein are useful in many aspects of ND
evaluation:
To validate or identify inconsistencies on Nuclear Data (ND)
To improve uncertainties and generate realistic covariances on ND
To produce new evaluations using Integral Data Assimilation methods
CEA Zero Power Reactors play an essential role in this context with a good
complementarity between mock-up experiments (EOLE, MASURCA), dedicated to the
experimental validation of calculation schemes, and nuclear data dedicated fundamental
experiments (MINERVE, EOLE)
| PAGE 8 Christophe Béhar | October 13, 2014
R&D ITEMS OF INTEREST FOR THE NEXT DECADES
There is a strong wish from CEA to maintain critical facilities in the next decades, as the
needs are well identified:
Support to Gen-II
• Cycle length, burnable poisons : higher enrichments, new poisons (Gd, Er,…)
• boron less PWR : higher gadolinium loads
• High temperature Doppler : Atomic Model impact, resonant slowing-down,…
Support to Gen-III
• in-core and ex-core instrumentation
• « Large core » effects : ND-targeted configurations
• Complementary experimental validation of Stainless Steel reflector :
• propagation,
• heating,
• dosimetry Survey,
• mixed loadings, interface effects (UOX/MOX in presence of SS)…
• Innovative assembly/fuel designs
| PAGE 9 Christophe Béhar | October 13, 2014
Support to Gen-IV
• V&V of advanced / innovative calculation schemes
→ From semi-analytical geometries to large SFR cores mock-up
MASURCA business
• Nuclear Data improvement
OECD/NEA report WPEC-SG 26 on target-uncertainties
→ Nuclear Data SFR-type coupled fast/thermal core , not possible
anymore in MINERVE
ZEPHYR
R&D ITEMS OF INTEREST FOR THE NEXT DECADES
| PAGE 10
Generic Support
• Nuclear Data improvement (not only for Gen-IV)
• Extension of calculation codes experimental validation (V&V of solvers and libraries) : going from
2D to local 3D effects, from 2 steps to 1-step core calculation
• Improvement of experimental target uncertainties (improvement of transposition): new or
enhanced experimental techniques, technological uncertainty management
• Development of instrumentation, calibration
• Modeling of degraded configurations, representative of accidental situations
• JHR “mock up”, in particular burnt samples and experimental devices
• Training and teaching activities
MASURCA
Christophe Béhar | October 13, 2014
THE ZEPHYR PROJECT
| PAGE 11
EOLE & MINERVE, both considered worldwide as being unique by their respective
flexibility, will be shut down at the end of 2019 (ASN decision)
In order to pursue R&D items as described, CEA needs a new ZPR: ZEPHYR
Zero power Experimental PHYsics Reactor
ZEPHYR is designed to be more flexible than EOLE and
MINERVE for nuclear data related experiments, especially
for Nuclear Data dedicated fast reactor applications
In Europe:
PROTEUS (PSI - Switzerland) is shut down
VENUS (SCK-CEN – Belgium) : 100% dedicated to MYRRHA
LR-0 (Czech Republic):100% dedicated to VVER
Christophe Béhar | October 13, 2014
JHR, AN INNOVATIVE MTR
| PAGE 12
Christophe Béhar | October 13, 2014
CONTEXT (why a new MTR in Europe?)
| PAGE 13
*
***
'
*
*
HBWR
OSIRIS
BR 2
under
construction
HFR
LVR 15
RJH**
OSIRIS
GW
Generation 3
Existing fleet40-year plant life
1980 1990 2000 2010 2020 2030 2040 2050 2060
Generation 3
Plant life extension
beyond 40 years
1980 1990 2000 2010 2020 2030 2040 2050 2060
Generation 4
Safety and Plant life time management (ageing & new plants)
Fuel behaviour validation in incidental and accidental situation
Assess innovations and related safety for future NPP: Gen 3 and Gen 4
Training of new generations
Existing technologies
PWR, BWR, …
Illustration
of nuclear
power
evolution in
France
The needs of a new brand MTR for R&D in
support to industry and regulators linked to
the evolution of nuclear energy:
Plant life time extension of GII reactors
Surge of GIII reactors
Preparation of GIV technology
The need of a new MTR because of an
ageing fleet of MTR in Europe (with
old safety standards)
The complementary needs:
Medical applications
(99Mo-99Tc / scintigraphy)
Christophe Béhar | October 13, 2014
R&D in support to nuclear Industry
Safety and Plant life time management (ageing & new plants)
Fuel behavior validation in incidental and accidental situation
Assess innovations and related safety for future NPPs (either LWR or GENIV concepts)
Radio-isotopes supply for medical application
MOLI production JHR will supply 25% of the European demand (today about 8 millions protocols/year) and up to 50% upon specific request
JHR will be a key tool to support expertise
Training of new generations Maintaining a national expertise staff and credibility for public acceptance Assessing safety requirements evolution and international regulation harmonisation
JHR 3 MAIN OBJECTIVES
Christophe Béhar | October 13, 2014 | PAGE 14
EXPERIMENTATION in MTR
| PAGE 15
MTR allows to reproduce on
a small scale, real power plant
conditions and in some cases,
more severe conditions for
Material screening (comparison of materials
tested under representative conditions)
Material characterisation (behaviour of one material in a wide
range of operating conditions, up to off-normal and severe conditions)
Fuel element qualification (test of one / several fuel rods (clad+fuel))
JHR
POWER PLANT
Circuits (thermohydraulic,
chemistry, purification,…)
In-pile test device
Fuels & materials irradiation
Christophe Béhar | October 13, 2014 | PAGE 15
JHR general design : a 100MWth pool type light water
MTR optimized for fuel and material testing
| PAGE 16
BR : Φ 37m H 45m
BAN : 51x47m H 35m
Pool : Φ 7m H 12m
About 200 aseismic pads Core Designed for UMo-Al fuel
Start-up with U3Si2-Al fuel
70 MWth / 100 MWth
25 to 30 days cycle length
6-7 days shutdown
Rooms dedicated to
reactor operation (heat exchangers, primary
pumps, safety systems,…)
Rooms dedicated to
reactor operation (control room, hot
workshop, labs,…)
Christophe Béhar | October 13, 2014
JHR CONSORTIUM & GOVERNING BOARD
JHR Consortium current partnership: Research centers & Industrial
companies
IAEC
Associated Partnership: NNL is the UK representative to JHR
UK/CEA agreement – March 2013
19/03/2007 Signature of the JHR
consortium
In some cases, the organization (member of the JHR consortium) is itself the
representative of a national consortium which gathers organizations among industry,
R&D organizations, TSO, or safety authority
JHR consortium gathers organizations which
take part financially in the construction of JHR
(1 representative / organization)
Christophe Béhar | October 13, 2014 | PAGE 17
CONCLUSIONS
Research reactors are essential both for current and future generations of NPPs
CEA is worldwide considered as a major research center and its research reactors are
key assets
Achieving JHR, Zephyr and MASURCA refurbishment aims to preserve this potential
within the framework of collaborations and associations (cf JHR consortium)
| PAGE 18 Christophe Béhar | October 13, 2014