pre0047-le coz pierre - international atomic energy …alstom power), jean-pierre biaudis ......
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www.cea.fr
Advanced Sodium Technologica l Reactorfor Indust r ia l Demonstra t ion
A S T R I D
DEN/CAD/DER/CPA
The ASTRID Project : Status and Future Prospects
Pierre LE COZ (CEA) – speaker
Jean-François SAUVAGE (EDF), Jean-Marie HAMY (AREVA NP), Vincent JOURDAIN
(ALSTOM POWER), Jean-Pierre BIAUDIS (COMEX NUCLEAIRE), Hiroyuki OOTA
(TOSHIBA), Thomas CHAUVEAU (BOUYGUES), Philippe AUDOUIN (JACOBS),
Daniel ROBERTSON (ROLLS-ROYCE), René GEFFLOT (ASTRIUM)
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13).
4 - 7 March 2012 - Paris, France
Paper CN-199-261
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 2
The ASTRID objectives
����Industrial technology demonstrator
����Integrating French and international SFRs feedback
����A GEN IV system
Safety :
- Level at least equivalent to GEN III systems (WENRA requirements)
- With significant improvements on Na reactors specificities issues
- Integrating FUKUSHIMA accident feedback
Operability :
- Load factor of 80% or more after first “learning” years
- Significant improvements concerning In Service Inspection & Repair (ISIR)
Ultimate wastes transmutation :
- Continue experimentation on minor actinides transmutation, up to large scales
if decided, according to June 28, 2006 French Act on Wastes Management
A mastered investment cost
����Irradiation services and testing long term
options
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 3
ASTRID general schedule
Open options : innovations and technological
breakthroughs are favored
consolidating the data to obtain a final and consistent design
Submission of a synthesis file to the French government
• January 2010 : the ASTRID project has been launched
and the first schedule has been defined
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 4
ASTRID - Preliminary design choices
1500 thMW - ~600 eMW
pool type reactor
With an intermediate sodium circuit
High level expectations in terms of safety demonstration
Preliminary strategy for severe accidents (core catcher4)
Diversified decay heat removal systems
Oxide fuel UO2-PuO2 for starting cores
Transmutation capability
4.
Main features mid 2010
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 5
Preconceptual design technical choices
• Integration of the electromagnetic pumps
in the design of secondary circuits
• Preferred lay-out :
• 3 primary pumps
• 4 intermediate heat exchangers
• 4 secondary circuits
• 4 decay heat removal circuits
• Conical "redan" inner vessel adopted
• Search for complementary and diversified
decay heat removal systems (no common
mode failure through the roof slab)
• Consider the possibility to prevent the
sodium fires by filling some zones with
inert gases
• Study of new concepts to decrease the fuel
loading-unloading duration
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 6
CFV core adopted for the conceptual design :
• Natural behaviour strongly improved to prevent
severe accidents
• Better natural behaviour to mitigate such
accidents
• Similar qualification program compared to SFR v2
core
THE LOW VOID EFFECT CORE
�Sodium void worth strongly reduced
�Quantification of the potential benefit
from safety point of view is ongoing
Absorbing protection
Sodium plenum
zone
Outer
fissile
zoneInner fertile zone
Upper inner fissile zone
Lower inner fissile zone
Fertile blanket
Neutronic protection
Absorbing protection
Sodium plenum
zone
Outer
fissile
zoneInner fertile zone
Upper inner fissile zone
Lower inner fissile zone
Fertile blanket
Neutronic protection
CFV core
T° = circa 900°C
T° = circa 700°C
Unprotected loss of heat sink (ULOHS)
SFR V2 = power circa 1100 MW at
the beginning of sodium boiling
CFV V2 = power circa 400 MW at the
beginning of sodium boiling
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 7
ACCESS taken into account from the early stage of the project
Slab penetrations
dedicated to ISIR
Access to the strongback
Isolation électrique
Lame arrière
Element piezo
Lame avant
BoitierCâble électrique
Tubes d’aération
US
Ecrou de serrage
Or
Brasures
CARRIERS DEVELOPMENTIn sodium and out of sodium
SENSORS DEVELOPMENTIn sodium and out of sodium
IN SERVICE INSPECTION AND REPAIR
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 8
� Two power conversion systems have been investigated
during the preconceptual design
� Steam PCS
• Most mature system based on a well-developed turbomachinery
technology.
• High plant efficiency.
• Studies on steam generators designs and leak detection
systems in progress with the aim of reducing the
risk of large SWRs and of limiting its consequences.
• Design and general lay-out will be done with steam PCS
during the conceptual design
• licensing safety assessment of a SFR must deal with
the Sodium Water Air reaction (SWAR): trend
to demonstrate a situation practically eliminated.
� Gas PCS
• Strong advantage as it inherently eliminates the SWR and SWAR risks.
• Very innovative option : major breakthroughs but feasibility and viability
not yet demonstrated.
• Remaining technological challenges but no show-stopper indentified.
• Studies will continue during the conceptual design to improve
performances, operability, maintainability and technology readiness
level
POWER CONVERSION SYSTEM
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 9
ASTRID safety approach
► The first Safety orientation document has been submitted to the French
safety Authority
► A Formal review will be led by experts in June 2013
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 10
Decay heat removal
• 2 direct reactor cooling systems: • Na/Na in the main vessel
• air as cold source,
• Redondancy : 2 ou 3 trains per system
(2*100% ou 3*50%)
• System n°1 : natural convection
• System n°2 : forced convection
• 1 complémentary system (mitigation): • Through the Primary Vessel Reactor
• Cold source to be confirmed (water / air)
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 11
ASTRID – Current organization
CEA/Nuclear Energy Division is the leader of the ASTRID project
CEA has concluded bilateral industrial partnerships to cover
main design engineering batches
� AREVA NP: nuclear island (core and fuel remains within CEA scope)
� EDF: support to the owner
� ALSTOM: turbine island
� BOUYGUES : civil engineering
� COMEX NUCLEAIRE: batches in robotics and mechanics
� TOSHIBA for development of large electromagnetic pumps
� JACOBS for the balance of plant
� ROLLS-ROYCE for innovations in fuel handling and heat exhangers
� ASTRIUM for RAMS methodologies
� Ongoing discussions with other French and international companies
CEA is willing to develop international partnerships for technical
developments and experimental facilities.
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 12
Project management team
Global design
CEA
GENIV strategic management
CEA/Nuclear energy directorate
ASTRID project industrial organisation
EDF support
En
gin
ee
rin
g
stu
die
s
AS
TR
ID
ma
na
ge
me
nt
ASTRID team
in MarcouleEDF R&D
InnovationsCOMEX NUCLEAIRE,
TOSHIBA
ROLLS ROYCE
External
assistances
AS
SIS
TA
NC
ES
R&D
Qualification of
the design (CEA)
Specific studies
Expertises (CEA)
Cadarache
Saclay
4Engineering
Batch 1
Engineering
Batch 2
Engineering
Batch N
Engineering
Batch N-1CoreCEA
Nuclear island
and I&CAREVA NP
Power con-
version system ALSTOM
Civil
EngineeringBOUYGUES
Balance
of plantJACOBS
Cad, Sac, Mar Lyon, Paris Belfort, Paris Paris
Cad, Sac, Mar
Paris
About 550 people
Lyon
Paris
Tokyo Marseille Derby
RAMSASTRIUM
Les Mureaux
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 13
2013: the beginning of the conceptual design
• Re-planning of studies due to new duration of conceptual design
• Cost analysing and starting technico-economical assessment:
� Options review
� Safety objectives requirements
� Reinterpretation of specifications requirements
• Finalising option reviews:
� General lay-out and Reactor Block Architecture
� fuel handling,
� Core catcher / Safety vessel, Activation level of secondary sodium
� containment (single or double-wall containment)
This phase could last until mid 2013
Need of a preparatory phase at the
start of AVP2
International Conference on Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios (FR13) 14
Oral sessions:
199/126 - sodium-water reaction
199/127 - Nuclear island
199/242 - core
199/262 - power conversion system
199/263 - Electromagnetic pumps
199/267 - Safety orientations
199/275 - architecture and lay-out
Poster session:
199/165 - In-Service Inspection and Repair
199/264 – project organization
199/265 - environmental steps
199/269 - start-up phase
199/274 - Instrumentation
Other ASTRID project papers