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THE ASTRID PROJECTAdvanced Sodium Technological Reactor for

Industrial Demonstration

FORTY-EIGHTH MEETING OF THE

TECHNICAL WORKING GROUP ON FAST REACTORS

25 – 29 MAY 2015

INSTITUTE OF PHYSICS AND POWER ENGINEERING

(IPPE)

RUSSIAN FEDERATION

MAY 2015

ASTRID | Alfredo Vasile

| PAGE 1CEA | 10 AVRIL 2012

OUTLINE

8 JUIN 2015 | PAGE 2CEA | MAY 2015

Objectives of ASTRID

The ASTRID program

Main technical options

Industrial and R&D organisation

Commissioning and Siting

THE ASTRID OBJECTIVES


Technological demonstration reactor (a step before a First Of A Kind)

Integrating French and international SFRs feedback

A GEN IV system

Safety

- Level at least equivalent to GEN III systems

- Progresses on Na reactors specificities

- Integrating FUKUSHIMA accident feedback

- Robustness of safety demonstration

Durability

- Need of Fast Breeder Reactors and a closed cycle

- Pu multi recycling to preserve natural resources

- Depleted uranium in FBRs allow producing electricity for few thousands of years

Operability

- Load factor of 80% or more after first “learning” years

- Significant progress concerning In Service Inspection & Repair (ISIR)

Ultimate wastes transmutation

- Perform demonstrations on minor actinides transmutation according to June 28, 2006 French

Act on Wastes Management

A mastered investment cost

Non proliferation warranty

Irradiation services and options test

THE ASTRID PROGRAM


R&D

Severe accidents

experimental program

Full scale component

testingLarge test sodium loops

Refurbishment of zero power

reactor MASURCA

Fuel fabrication workshopMOX fuel

A few tons per year

ASTRID design studiesIntegrated Technology Demonstrator

600 MWe

4th generation reactor

Irradiation tool

ASTRID CONCEPTUAL DESIGN MAIN

CHARACTERISTICS


• Nominal power 1500 MWth - ~600 MWe

• Pool type reactor

• With an intermediate sodium circuit

• CFV core (low sodium void worth)

• Oxide fuel UO2-PuO2

• Strategy for severe accidents (in vessel core

catcherH)

• Diversified decay heat removal systems, 5 circuits.

• Fuel handling in gas, internal storage

• Conical "redan" inner vessel adopted

• Lay-out :

� 3 primary pumps

� 4 intermediate heat exchangers

� 4 secondary circuits

• Experimental capabilities: to contribute to the

qualification of transmutation, in blankets or burner

subassemblies

� Open design option: energy conversion system

ASTRID MAIN INNOVATIONS


Low void coefficient core with

enhanced safety (« CFV »)

Tertiary circuit with nitrogen

to prevent any sodium-water

reaction

In-Service Inspection

addressed from the

design phase

Provisions for core melt management

(no early or significantant radiactive

release)

LOW VOID EFFECT CORE (CFV)


Objectives :

Reduced reactivity loss

Negative sodium void worth

Favorable behavior in non

protected transients

Removable axial

neutronic protection

144 internal storage

positions

Plénum sodium

Zone fissile interne (U,Pu)O2

Zone fissile interne (U,Pu)O2

Plaque fertile (UO2)

Couverture fertile (UO2)

Zone fissile

externe (U,Pu)O2

Protection neutronique en B4C

Axe cœur

REACTIVITY CONTROL SYSTEMS


All the rods are used for reactor operation: control rods (RBC) and diversified rods (RBD)

Addition of complementary diversified safety devices : hydraulics ones (DSC-P)-H and

Curie point thermal ones (DCS-P)-T

Curie point

electro magnet

� JAEA

design

3 DIVERSIFIED DECAY HEAT REMOVAL SYSTEMS


Third heat removal system

through reactor vessels for

severe accidental conditions

- Oil coolant

- Water heat sink

2 diversified in-vessel decay

heat removal systems

- Passive in the hot reactor

plenum (3 trains x 66%)

- Active in the cold reactor

plenum (2 trains x100%)

- Na coolant

- Air heat sink

IN-CORE COMPLEMENTARY SAFETY DEVICES

FOR SEVERE ACCIDENTS MITIGATION (DCS-M)


CFV core equipped with 21 devices for corium dispersion

Objectives:

Reduce re-criticality risk

Avoid melting propagation to the internal storage

Minimize impact on core performances

� 21 Tubes crossing diagrid and strongback (DCS-M-TT)

Sommier

Platelage

Cœur

Fissile

P

N

L

Core-catcher

DCS-M-TT

CORE-CATCHER


In-vessel core-catcher

Metallic plate

Protected by 400mm ZrO2

Whole core plus 3 reflector rows

Reactivity mastering

Corium spreading

Addition of absorbing materials if

necessary

Cooling mastering

Cooling by sodium natural

convection around the core-catcher

Corium transfer by the DCS-M-TT to the

core-catcher

Core-catcher sktech

GAS ENERGY CONVERSION SYSTEM


Steam-water energy conversion system is considered for global evaluations in order to

provide a solid basis of comparison for costs evaluation and safety analysis, and to get a

reference configuration for all the partners to work on a common basis

Gas energy conversion system is the priority domain of design and R&D in order to

increase its maturity level

A 2 shaft turbomachinery line have been retained based on a technical-economical

analysis

GAS ENERGY CONVERSION SYSTEM


37% efficiency

Operation and safety analysis have been performed

� No show-stopper identified at that point

CompressorTurbine

Compact sodium gaz heat exchanger

CEA

Brayton gas cycle : 180 bar

of Nitrogen at 515°C

ASTRID SCHEDULE


2010 2011 2012 2013 2014 2015 2016 2017 2018 2019 2020 2021 2022 2023 2024 2025 2026 2027

Preconceptual

designBasic design Detailed design and Construction

Tests

First

criticality

Connection

to the grid

Decision

to launch the

conceptual

design

Conceptual design

Decision

to launch the

basic designDecision

to build

Safety

orientations file

Safety options

filePreliminary

safety report

ORGANISATION OF THE ASTRID PROJECT IN THE

CONCEPTUAL DESIGN PHASE

| PAGE 15CEA | MAY 2015

Contracting authority

Strategic management

ASTRID project team

Operational management

Industrial architect EDF assistance

Desig

n

Astr

id M

anagem

ent

ASTRID relay team in

Marcoule

Search for innovations

Reactor core Nuclear Island Power conversion

systems

External assistance

R &

D

Civil

engineering

Balance of plant

and infrastructures

Reliability,

availability,

maintenability

Hot cells

European R&D labs

/R&

D

Assis

tance

R&DInnovation,

Qualifications, Codes,

Specific developments,

Expertises

About

600 people

EUROPEAN AND INTERNATIONAL COOPERATION

| PAGE 16CEA | MAY 2015

European Framework (FP7, H2020, EERAD)

Relevant projects on SFR R&D and in support to ASTRID

• Dedicated to SFRs: EISOFAR, CP ESFR

• Crosscutting projects for Gen IV reactors: ADRIANA, GETMAT,

MATTER, SARGEN IV, SILER, THINS, ANDES, ESNII+,

MATISSE, SESAME, SAFEST,H

European R&D related to safety requirements for ASTRID

Large R&D needs

Bilateral cooperations in the framework of ARDECO with:

EDF R&D, PSI, KTH, Chalmers, Uppsala, HZDR, KIT,

ENEA, JRC/ITU, NNL, CIEMAT, ...

Other international

Russia, USA, Japan, Korea, India, China

R&D

International

THE MAIN OBJECTIVES TOWARDS THE END

OF THE CONCEPTUAL DESIGN


Many options selection reviews still to come

The safety option file

The security option file

The up-date for mid of 2015 of the 2012 ASTRID report to the government

The Project review for the choice of the Energy Conversion System: november 2015

A convincing and coherent conceptual design final report

CONCEPTUAL DESIGN FILE

(TO BE ISSUED END 2015)


- Synthesis reports:

� ASTRID description, performances, content of the conceptual design file

� Systems technical specifications (STB)

- 3D mock-up for the water model (AST-V)

- Report gathering all the studies on the gas energy conversion system

- Preliminary evaluation of ASTRID cost

- Provisional planning of realization

- Project risks analysis

- Safety Option Report (DOS)

- Security Option Report

- Codes and norms basis for ASTRID

- Qualification roadmap for scientific calculation tools (OCS)

- Preliminary plan for ASTRID definition:

� Design choices justification

� Performances justification (including safety, operability and inspection capabilities)

� Needs for R&D and components qualification

- One synthesis file per partner

� Indicative number of issued documents (pre and conceptual design) : 2350

- Synthesis reports:

� ASTRID description, performances, content of the conceptual design file

� Systems technical specifications (STB)

- 3D mock-up for the water model (AST-V)

- Report gathering all the studies on the gas energy conversion system

- Preliminary evaluation of ASTRID cost

- Provisional planning of realization

- Project risks analysis

- Safety Option Report (DOS)

- Security Option Report

- Codes and norms basis for ASTRID

- Qualification roadmap for scientific calculation tools (OCS)

- Preliminary plan for ASTRID definition:

� Design choices justification

� Performances justification (including safety, operability and inspection capabilities)

� Needs for R&D and components qualification

- One synthesis file per partner

� Indicative number of issued documents (pre and conceptual design) : 2350

INTERACTIONS WITH THE FRENCH NUCLEAR

SAFETY AUTHORITY (ASN)


The ASTRID safety orientations submitted in June 2012

Review by Expert Committee on Reactor Safety in June 2013

Letter by the ASN in April 2014

The safety orientations take into account the SFR feedback of experience in a satisfactory

manner

No objection to continue the project on the basis of the safety orientations proposed by CEA

Safety level at least equivalent to EPR type reactors and taking into account lessons from

Fukushima accident

Review of 6 GIF systems by the Expert Committee on Reactor Safety on

April 10th, 2014

“Among the nuclear systems studied by the GIF, only the SFR presents a sufficient maturity to

envisage the realization of a 4th generation industrial prototype in the first half of the 21st

century”

XXX


PHENIX

CEA

Marcoule Center

ASTRID

candidate

site

CONCLUSIONS


CEA and its industrial and international partners, are progressing on the conceptual design

of ASTRID.

Very satisfactory feedback on the ASTRID safety orientations by the Expert Committee on

Reactor Safety and ASN.

The current conceptual design phase is the opportunity to further develop our collaborations

on design and/or R&D activities.

Next important milestones:Mid 2015: update of the report on research carried out on the separation and transmutation of long-

lived radioactive elements, and on the development of a new generation of nuclear reactors (French

Act of 2006 on waste management)

End of 2015: end of ASTRID conceptual design, Safety Options Report

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