SFR Safety Considerations. Jean-Paul Glatz, EC-JRC-ITU, EURATOM

Transcription

1 SFR Safety Considerations Jean-Paul Glatz, EC-JRC-ITU, EURATOM Impact of the Fukushima Event on Current and Future Fast Reactor Designs, HZDR March 2012

2 FP7 Euratom program European Nuclear Energy Concept Strategic Energy Technology SET Plan Sustainable Nuclear Energy Technology Platform (SNE-TP) European Sustainable Energy Industrial Initiative (ESNII) ESFR and GIF SFR System Nuclear accident research

3 3 main pillars + key cross-cutting issues Maintain safety and competitiveness of today s technologies Fukushima impact: SNETP gives nuclear safety the highest priority in its vision and research agenda ESNII ESNII = European Sustainable Nuclear Industrial Initiative Enlarge the nuclear fission portfolio beyond electricity production (H 2, synthetic fuels, petrochemical/ steelmaking/ paper/ cement industries, seawater desalination, etc.) Develop advanced reactors with closed cycle to enhance sustainability

4 FP7 EURATOM program : Nuclear fission and radiation protection: 118 M JRC nuclear research activities: 233 M Fusion energy research: 2.2 B 1 call each year with ~50 M /y with deadline in April- May In calls, move away from catch-all topic to targeted topics selected from SNE-TP prioritisation list

5 5th Call Fission Call Identifier: FP7-Fission-2011 Publication Date: 20 August 2010 Indicative Budget: M 41 Deadline: 07 April 2011 Management of radioactive waste: Support for future IGD-TP vision/sra Reactor systems: Support for SNE-TP SRA Support for ESNII of SET-Plan Radiation protection: Support for MELODI initiative Human resources, E&T, Infrastructures, International cooperation

6 Reactor Systems European Gas Cooled Fast Reactor GOFASTR Liquid Fuel Fast Reactor System EVOL European sodium fast reactor CP-ESFR Seismic-Initiated LEad-cooled Reactors SILER Advanced systems for non electrical uses ARCHER SCWR fuel qualification tests SCWR-FQT Cross-cutting aspects for nuclear systems R&D activities in support of the implementation of SRA of SNE-TP MAX, FREYA Coordination and support of Euratom contribution to GIF Material research (EERA) MATTER, GETMAT Fuels F-BRIDGE Safety ASAMPSA2, SARGEN, TRASNUSAFE Reliability of programming for automation HARMONICS Accidents SARNET2, ALISA Nuclear education and training ECNET ENEN-RU Cooperation with Third Countries:China

7 European Sustainable Nuclear Industrial Initiative CP ESFR SFR Reference (proven) technology SFR Prototype Astrid MWe 5 b LFR GFR Alternative technology Supporting infrastructures, research facilities, irradiation facilities & fuel manufacturing and reprocessing facilities 2.8 b LFR demonstrators MYRRHA ALFRED Allegro GFR Demo Test bed of GFR technologies Innovative fuel MA transmutation Coupling to heat applications MA fuel micropilot 2040: Target for 1.9 b deployment of Gen-IV Fast Neutron Reactors 1.3 b or earlier if new energy needs (electric vehicles, process heat applications) MOX fuel fab unit Total estimated cost: 11 b

8 CP ESFR GIF-SFR links: Executive Board: decision on responsibles for project interactions Deliverables from CP ESFR being proposed to SFR PMBs identified For the fuels project significant overlap with European projects (e.g. F-BRIDGE) Corium relocation strategy should be implemented Focus on pool type only CD&BOP: focus on optimisation of energy conversion and heat transfer systems E&T with a large number of trainings on Na handling (Cadarache) and numerous phds within the project

9 CP ESFR technical subprojects GIF SFR management boards EURATOM rep. in the GIF/SFR MB CP ESFR liason SP0 management SFR steering committee J.-P. Glatz/ A. Vasile A. Vasile/ A. Tosello SP1 consistency& sytem integration and H. Tsige-Tamirat/ A. Vasile/ assessment assessment (SIA) J.-P. Glatz R. Stieglitz SP2 fuell & fuel cycle advanced fuels (AF) J. Somers/ A. Menna J.-M. Bonnerot/ J. Somers SP3 PRPP/safety & operation safety and operation A. Vasile/ D.V erwaerde/ (SO) (SO) V. Ranguelova D. Stieglitz SP4 innovative architectures, components& BOP CD&BOP A. Gerber/ R. Stainsby B. Riou/ R. Stainsby SP5 education and training C. Latgé/D. Cacuci

10 Gen IV SFR Large pool reactor track

11 Gen IV SFR Large pool reactor track 1 Row of Steel Reflectors or Assemblies with Fertiles or Minor Actinides Inner core Fuel Assembly Outer core Fuel Assembly 2 Rows of Steel Reflectors CSD (Control and Shutdown Device) DSD (Diversified Shutdown Device)

12 Electric/Heat output 1500MWe/3600 MWth Fissile volume (m 3 ) 17.4 Outer core radius (cm) 245 Fissile height (cm) 100 Power density (W/cm 3 ) 206 Pu content by zone (% vol) 14.5 / 16.5 Fissile height (cm) 100 Fuel residence time (efpd) Average Burnup (GWd/t) 100 Pin diameter (mm) 10.7 Number of pins 271 Mass UPuO 2 (t) 79 Plant lifetime 60 years

13 Secondary loop SG modules Pump IHX

14 Evaluation of ESFR for Generation-IV metrics Gen-IV System Evaluation Tool was utilized 26 metrics relate to the Gen-IV goals Sustainability Proliferation resistance Safety and reliability Economics

15 Safety & Reliability Goals Rollup Safety and reliability 0,6 0,5 0,4 0,3 0,2 0,1 The ESFR system has the potential to be highly reliable and achieve forced outage rates as low as LWRs. important reduction in routine radiological exposure to plant personnel in comparison with LWRs. Routine exposures are likely to be lower in fast reactor plants due to greater confinement and lesser degree of activated corrosion products. radiological exposure from accidents is reduced in SFRs, due to unpressurized primary and secondary heat transport systems. Power and temperature coefficients are inherently negative. 0

16 Objectives of the Safety and Operation Project analysis and experiments that support approaches and assess performance of specific safety features, development and verification of computational tools and validation of models employed in safety assessment and facility licensing, and valorisation of reactor operation, from experience and testing in operating SFR plants.

17 Scope of Safety and Operation Project Safety <R&Ds supporting safety assessment> Passive/active safety Severe accident Safety architecture Reactor Operation Technology and Testing (ROTT) <R&Ds through operation and testing of existing reactors> Phenix (France) Monju (Japan) <Feedback of decommissioning of LMFR> Rapsodie, Phenix, Superphenix (France)

18 Utilization of Data from Existing SFRs Data Acquisition and Operational Feedback Experiments and Testing for Design and Safety Tools Validation Demonstration of Advanced Technology Assurance of Passive Safety Response Investigation of Phenomena Axial Fuel Expansion Radial Core Expansion Investigation of Design Features Self Actuated Shutdown System Passive Decay Heat Removal System Techniques for Evaluation of Bounding Events Investigation of Phenomena/Design Features to Prevent and mitigate Severe Accident Progression

19 Reactor Accident Research at ITU Three Mile Island a real accident - an integral test (with incomplete data) Phebus FP test integral test with good data collection but still difficulties in interpretation Corium interaction Thermochemistry/SARNET small scale tests of liquid Zry dissolution of UO 2 fuel Revaporisation testing single effect tests of volatilisation of fission products under different atmospheres

20 Phebus PF program International project lead by the Institut de Protection et Surêté Nucléaire (IPSN now IRSN) and supported by the European Commission. Other non-e U Countries participating (USA, Canada, Japan, Korea and Switzerland). FPT0 1993: (base-line test) degradation of a non-irradiated, 20 x 1m fuel rod bundle FPT1 1996: 18 fuel rods (23 GWd/tU) under a similar steam atmosphere. FPT2 1999: 18 fuel rods (23 GWd/tU) under poor steam atmosphere. FPT3 2000: similar to FPT2 with B4C control rods instead of Ag-In-Cd FPT4 2004: similar to FPT2 with EdF fuel (~33GWd/tU) no re-irradiation ITU contributions: i) sectioning of degraded bundle into 14 x 2cm thick discs ii) microscopic examination and analysis of phases at selected points iii) examination of PTA samples (filters)

21 Applications and future use of this work Compilation of data - often as stability diagrams E-pH (Pourbaix) diagrams, or po 2 -T (Ellingham) diagrams, or composition phase diagrams Derivation of mechanisms and kinetics and deciding thresholds for input into models or codes: this reaction information -----> mechanistic modelling Data correlation -----> can give general information as to reactor accident behaviour -----> empirical modelling example of modelling application - ASTEC suite of codes being developed at Cadarache - trying to generate the missing or replace inadequate data

22 Impact of Fukushima EURATOM research programs Council of the European Union Consensus to have a European approach on safety Conduct comprehensive safety and risk assessment (stress tests) to re-assess safety margins of NPPs in the EU SNETP reaction Solidarity to the people of Japan and support to TEPCO and Japanese authorities in their efforts to limit consequences of accident The GB decided to set up a dedicated TF to assess the lessons from Fukushima to identify adaptations of SNETP s WP FP8 research program with major focus on safety aspects (follow-up of ESFR SOFIA. Safety European research for the Gen IV prototype Astrid GIF SFR: enhanced activities in safety Renewed interest in nuclear accident research programs

23 Joint Research Centre (JRC) Contact: Serving society Stimulating innovation Supporting legislation 23