ASTRID core Design objectives, design approach, and R&D in support

Transcription

1 ASTRID core Design objectives, design approach, and R&D in support G. Mignot - ASTRID Project Gerard.mignot@cea.fr N. Devictor - SFR R&D Project nicolas.devictor@cea.fr 1 Vienna February

2 Content ASTRID project Core design objectives R&D program in support to the core design That talk is completed by the following talk «PRE-CONCEPTUAL DESIGN STUDY OF ASTRID CORE» 2 Vienna February

3 Advanced sodium technological reactor for industrial demonstration Industrial prototype (step before a First Of A Kind) Integrating French and international SFRs feedback A Generation IV reactor Safety : Level at least equivalent to GENIII systems + lessons learnt from Fukushima accident With significant improvements on sodium specific issues Operability : Validate on the long term an ambitious load factor Significant improvements concerning ISI&R 3 Ultimate waste transmutation : Continue experimentation of minor actinides transmutation, up to large scales if so decided An investment cost under control Irradiation services and testing of longer term options IAEA TECHNICAL MEETING ON INNOVATIVE FAST REACTOR DESIGNS 3 WITH ENHANCED NEGATIVE REACTIVITY FEEDBACK FEATURES Vienna February

4 The ASTRID program ASTRID design studies SFR industrial prototype 600 MWe Irradiation tool Core fabrication workshop MOX fuel A few tons per year Full scale component testing Refurbishment/Realization of large test sodium loops Refurbishment of zero power reactor MASURCA Severe accidents experimental program + R&D (including fuel cycle) Feasibility study for minor actinides bearing experimental fuel fabrication 4 Vienna February

5 Schedule for ASTRID and associated facilities Preliminary choice of options Decision to continue Decision to build Fuel loading ASTRID Pre-conceptual design Conceptual design Basic design Detailed design & Constructi on Facilities Position Report on minor actinides partitioning and transmutation Core manufacturing workshop (AFC) MA bearing fuels fabrication facility 5 Vienna February

6 Pre-conceptual and conceptual design Mid of 2010 : preliminary selection of ASTRID characteristics for launching the pre-conceptual design The pre-conceptual design will be delivered by the end of 2012 The pre-conceptual design will consider some open options. Innovation and technological breakthroughs will be favored, while maintaining risk at an acceptable level. During the pre-conceptual design phase, start of the interactions with the Safety authorities on safety objectives and orientations. The conceptual design will be delivered by the end of 2014 During the conceptual design phase, the ASTRID design choices will be finalized and the Safety Option File will be submitted. 6 Vienna February

7 ASTRID : preliminary design choices / open options 1500 MWth, ~600 MWe reactor Pool type reactor With an intermediate sodium circuit Preliminary strategy for severe accidents (core catcher ) Oxide fuel for starting cores Transmutation capability High level expectations in terms of safety demonstration In sodium fuel handling Main features Many of these options will be decided during the pre-conceptual design up to 2012, some will remain open and be decided during the conceptual design. Open options Energy conversion system Reference : water/steam Alternative : N2 Number of loops Devices to eliminate severe accidents (i.e. 3rd shutdown level) Corium catcher technology SGs materials and technology Innovative technologies for Na fires detection and extinction I&C Carbide Fuels SiC-SiC Materials Innovative options to be tested 7 Vienna February

8 Core design approach ASTRID core design is mainly guided by safety objectives : 1. Prevention of the core meltdown accident To prevent meltdown accidents -by a natural behavior of the core and the reactor (no actuation of the two shutdown systems) -with adding passive complementary systems if natural behavior is not sufficient for some transient cases 2. Mitigation of the fusion accident To garantee that core fusion accidents don t lead to significant mechanical energy release, whatever initiator event -by a natural core behavior -with adding specific mitigation dispositions in case of natural behavior is not suffficient 8 Vienna February

9 Core design objectives Natural behavior favorable for transients of unprotected loss of flow and loss of heat sink Target criteria : no sodium boiling for a ULOSSP transient Sodium void effect minimized Target criteria : Na void effect < 0 Natural behavior favorable for a complete control rod withdrawal (with no detection) Target criteria : no fuel fusion Improved performances Target criteria : Cycle length 480 efpd, High fuel burnup, and breeding gain 0 + Core design is extrapolable to higher power 9 Vienna February

10 Core designs options : SFRv2 and CFV concepts SFRv2 core CFV core Absorbing protection Sodium plenum zone (Patent) Feedback experience from SPX and EFR : To reduce the fuel reactivity loss per cycle To reduce the sodium void worth Fuel rod diameter increased Spacer diameter reduced 2008 : concept with larger pin and smaller-diameter spacing wire - Increase of the fuel fraction - Low reactivity loss during cycle -Decrease of the Na fraction lower Na voiding effect Improvement on control rod withdrawal Upper inner fissile zone Inner fertile zone Lower inner fissile zone Fertile blanket Outer fissile zone Neutronic protection 2009 : heterogeneities added to SFRv2 core Sodium void worth strongly reduced Quantification of the potential benefit from safety point of view is on going 10 Vienna February

11 Information on R&D done in support to ASTRID core design 11 Vienna February

12 R&D in support to design - Subassembly Design for «stable boiling» in case of ULOSSP PNS PNS Example of CFV Na Na Mechanical behavior Plug VES Plug VES Thermal gradient Fissile Fertile Fissile Fissile CAI CAI VEI VEI Plug, etc. Plug, etc. Heterogeneous SA Homogeneous SA 12 Vienna February

13 R&D in support to design - Subassembly Materials for first cores Clad : 15/15Ti / AIM1 Hexcan : EM10-9Cr 1 Mo R&D on thermomechanical behavior of fuel material for high temperatures Assessment for the possibility to use a positive effect on reactivity from the pad flowering R&D on cladding Smaller diameter for spacing wrapper Need for low swelling materials : R&D on F/M ODS steels Improvment of performance of fuel (expertise of irradiated SA in Phenix) Enfoncement élastoplastique des plaquettes d'un assembage CFV V0 à 800 C 5000 Force moyenne sur plaquettes opposées en N assemblage calcul élastique assemblage calcul plastique parfait (s0 = 90 MPa) assemblage calcul plastique parfait (s0 = 45 MPa) CEA ODS tube Enfoncement plaquette en mm 13 Vienna February

14 R&D in support to design - Subassembly Objective to detect abnormal movement and to prevent compaction leading to insert almost 1$ Review of design options for pad and Foreign options R&D on Fluid Structure interactions + cooperation with IGCAR 14 Vienna February

15 R&D in support to design - Subassembly In case of a beginning of sodium boiling at the top of fissile area, we would like to demonstrate that the sodium boiling could be stabilized R&D on SA design, on modeling + Experimental support Water/gas : SENSAS facility With sodium? 15 Vienna February

16 R&D in support to design - Absorbers SEPIA (patent) Development of 3 rd passive system independent of control rods 16 Vienna February

17 Simulation Neutronics (PARIS/ERANOS currently) Decay heat removal (CATHARE TrioU_MC2) Mechanical behavior of bundle and hexagonal tube (HARMONIE, CAST3M ) Design of SA and absorbers (PLEIADES) Development of coupled simulation better understanding of margins transients 17 Vienna February

18 Simulation CFD «System code + CFD» (development + validation) System code: Cathare 18 Vienna February

19 Simulation Core degradation Development and Validation of Severe Accidents codes (CABRI, JAEA EAGLE program ) SAS4A / SAS-SFR SIMMER III/IV Applications in support to SFRv2 CFV comparison 19 Vienna February

20 Inlet and outlet core temperature T, CRW (TIB?) TC, optical fiber, flowmeter Surveillance and Protection Surveillance ciel de pile Gaseous FP Core CFV Chambre d ionisation, Spectro γ, (CRDS) Clad failure Localisation in gaz Gaseous FP Ionisation chamber, Spectro γ, (CRDS) Acoustic Detection Abnormal noise (TIB?) Innovative Line of Defense A ( ) R&D Inlet and outlet core flowrate TIB, loss of flow Active Acoustic Det. Gas rate SONAR, TUSHT 20 Neutronic monitoring Fonctionnement, CRW High Temperature Fission Chambers with large dynamics Clad Failure Detection in Na Open CF, BTI HTFC / IHX Clad failure Localisation in Na FP neutronic detection FC with B US telemetry under Na Core movment, (Temperature) Vienna February

21 Development of experimental facilities CHEOPS - SA qualification TH mock-up CORRONA Refurbishment MASURCA 21 Vienna February

22 Transmutation 2 axis are studying : Homogeneous recycling GenIV GACID Program Heterogeneous recycling CCAm Prototyping irradiations for acquiring knowledge on gas behavior (He ), MARIOS (in HFR reactor from March 2011 to April 2012) DIAMINO in OSIRIOS from mid of IAEA TECHNICAL MEETING ON INNOVATIVE FAST REACTOR DESIGNS CINNA WITH GGP ENHANCED R4G 12/10/11NEGATIVE REACTIVITY FEEDBACK FEATURES Vienna February

23 R&D: co-operations EDF and AREVA Part of the R&D is supported by several international cooperations European co-operations EC programs as for example EERA, PCRDT (CP-ESFR, ADRIANA, GETMAT, FAIRFUELS, SARGENIV, ASAMPSA2, THINS, MATTER, etc.) CEA SRC (Swedish Research Council) agreement Rolls-Royce KIT, ITU, ENEA, PSI, IAEA by contribution of several CRP, as for example on some PHENIX End Of Life Test, passive systems, and also INPRO GIF(CD&BOP, Safety & Operation, GACID ) Co-operations with IGCAR, JAEA, US DOE, CAEA, Russia, KAERI 23 Vienna February

24 Thank you for your attention Commercial reactor ASTRID RAPSODIE Vienna February