PRESENT STATUS OF FRENCH PROGRAM ASTRIDJAPAN FRANCE COOPERATIONEXPECTATIONS ON MONJUMONJUASTRIDALAIN PORRACCHIADIRECTOR FOR INNOVATION AND INDUSTRIAL SUPPORTCEA/DEN

French R&D programon SFR and the| PAGE 1

WHY TO CHOOSE A FAST NEUTRON REACTOR ?

Three main reasons:• Mastering, through recycling, the growth ofPlutonium inventory• Excellent use of uranium resource
Unlike reactors currently in operation or construction worldwide,that use only about 1% of natural Uranium, Fast neutron
Reactors are able to use more than 80% of the Uranium
resource.
The current stockpile of depleted Uranium available in France
could feed the current needs of electricity production for several
1000 years.

• Ability to transmute and burn minor actinides
Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division| PAGE 2

A PERFECT CONVENIENT TECHNOLOGY FOR THE FUTURE
Two types of Fast Neutron Reactors have been selected in France:• Cooled by sodium : the reference
The ASTRID Project

Integrated Technology
Demonstrator
600 MWe
4th generation reactor• Cooled by gas : the prospective route
The ALLEGRO Project, a project embodied
through a consortium in central Europe
CEA Associated to the Consortium

Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division| PAGE 3

ASTRID AND FUEL CYCLE SCHEDULE

Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division| PAGE 42006 FRENCH ACT : THE 2012 MILETSONE

Executive Summary available in English end of May
Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division| PAGE 5

GENERAL FRAME OF THE ASTRID DESIGN• ASTRID will be designed using lessons learnt from the
Fukushima-Daichi accident• The design benefits of feedback of Sodium-cooled fastneutron reactors
Favorable intrinsic features to cool-down the reactor: Largethermal inertia; Diversified heat sinks; Natural circulation;
Ability to guarantee a minimum sodium level.

• Safety objectives of ASTRID are derived from theWENRA* document “Safety objectives for new nuclearpower plants”.
It summarizes the highest safety standards, even for
Fukushima-like initiators. Former Beyond Design BasisAccidents are included in the design.
*Western European Nuclear Regulators Association• Safety requirements are checked with the Generation IV
International Forum Safety Design Criteria
Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division| PAGE 6

PRELIMINARY DESIGN CHOICES / OPEN OPTIONS(AS FOR APRIL 2013)

Main features

Open options

1500 thMW - ~600 eMW
Sodium cooled pool type reactor
3 Primary pumps, 4 IHX
4 Secondary sodium loops with EMPs
Oxide fuel UO2-PuO2
High level expectations in terms of safety
demonstration- Preliminary strategy for severe accidents(core catcher…)- Diversified decay heat removal systems
Fuel handling in sodium….

Core design
Energy conversion systemwater/steam or
N2 (reference today)
Complementary devices for improved
prevention of severe accidents (i.e. 3rdshutdown level)
Core catcher design and materials
SGs or Sodium-Gas HX design andmaterials
Innovative technologies for Na fires
detection and mastering
Type of I&C…..
Innovative
options to be tested--Carbide fuel
SiC-SiC materials…
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Alain Porracchia, CEA - Nuclear Energy Division| PAGE 7

ASTRID PROJECT INDUSTRIAL ORGANIZATION
About 550 people

ASTRID
management

GENIV strategic management
CEA/Nuclear energy directorate
SaclayR&D andASSISTANCES

Externalassistances
EDF R&D

Project management team ASTRID teamin Marcoule
Global design
CEA
EDF support

Paris

R&D
Qualification of
the design (CEA)
Specific studies

Lyon

CadaracheCad, Sac, Mar

Innovations
RAMS

Expertises (CEA)COMEX NUCLEAIRE,TOSHIBAROLLS ROYCEASTRIUM
Les MureauxEngineeringstudiesTokyo Marseille Derby

Engineering
Core
Batch
CEA1

NuclearislandEngineering
andI&C2
Batch

Power conversion…system

AREVA NP

ALSTOM

Lyon, Paris

Belfort, Paris

Cad, Sac, Mar

Monju International Workshop - April 25, 2013

CivilEngineering
Engineering
Batch N-1
BOUYGUES

Alain Porracchia, CEA - Nuclear Energy Division

ParisBalance
EngineeringofplantN
Batch
JACOBSParis| PAGE 8

FROM LWRs RECYCLING TO FRs RECYCLING
Pu stored in MOX Spent
Fuel recycled in MOX
SFR to start the SFRs
deployement

Scenario can be flexible
Both systems can coexist
during a transition phase• FNR merits as regards to fuel cycle
No front end steps and no enrichment technology
Use depleted U; Use Pu included in MOX Spent Fuel
Multi-recycling of Pu
Possible recycling of Minor Actinides
Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division

Possible
irradiationin Monju ?
9 | PAGE 9FRANCE JAPAN COOPERATION ON ASTRID - MONJU

Three areas of cooperation-1. Astrid Fuel
-2. Sharing Programs and Infrastructures
Joyo-3. Participation to Astrid R&D and Studies
RJH
Monju

A Comprehensive Cooperation Program under construction
And already long term story beween Japan and France
on Sodium Fast Reactors
Monju International Workshop - April 25, 2013

| PAGE 10MONJU ROLE / FRANCE VIEW

NEEDS•ASTRID DRIVER FUEL QUALIFICATION•PLUTONIUM MULTIRECYCLING QUALIFICATION•MINOR ACTINIDES TRANSMUTATIONTrilateral Framework with US (GACID and New GACID)
Mentioned in the national
report released end 2012

Strong Expectations on Large Scale Irradiations Programs• Full Size Pin• Bundle• Sub-AssemblyMonju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division| PAGE 11

Thank you| PAGE 12Commissariat à l’énergie atomique et aux énergies alternatives

French R&D program

Centre de Saclay | 91191 Gif-sur-Yvette Cedex
T. +33 (0)1 68 09 32 04
Etablissement public à caractère industriel et commercial | RCS Paris B 775 685 019

Nuclear Energy Division

LONG TERM SUSTAINABLE SYSTEMS

1. KEEP ON RECYCLING in NUCLEAR SYSTEMS
2. IN FAST REACTORSEFFICIENT BURNING OF PLUTONIUM
NO NEED FOR NATURAL URANIUM
POTENTIAL FOR IMPROVING WASTE MANAGEMENT

Because ofthese main
merits :PWRs andSFRs

1.00
0.90
0.80
0.70
0.60
0.50
0.40
0.30
0.20
0.10
0.00

PWR

Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy DivisionCm244Am243Am
24
1P
u242P
u241

P
u240

P
u239

Pu238

Np237

SFRU
238U23
5Fission/Absorpt

Fission/Capture rate for various nuclides in| PAGE 13

A BETTER USE OF URANIUM 238

Source : WEC, 2010 Survey of Energy. (Coal: 860 Gt, Oil: 163 Gt, Gas: 185 Tm3, Uranium : 3,5 Mt)

Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division

14RADIOACTIVE WASTE OF GENERATION IV SYSTEMS

Monju International Workshop - April 25, 2013

Alain Porracchia, CEA - Nuclear Energy Division| PAGE 15