Overview of IAEA Activities in Support of Fast Reactors Development and Deployment & Objectives of this Meeting

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1 Technical Meeting to Identify Innovative Fast Neutron System Development Gaps HQ, Vienna, 29 February 02 March 2012 Overview of Activities in Support of Fast Reactors Development and Deployment & Objectives of this Meeting Stefano Monti Nuclear Power Technology Development Section Division of Nuclear Power International Atomic Energy Agency

2 Summary FR programme and the role of the TWG-FR Coordinated Research Projects in the field of FR FR-related Technical Meetings and Publications Objectives of this Technical Meeting 2

3 Main activities of the Programme on Fast Neutron Systems (1/2) Organize regular Topical Technical Meetings for in-depth information exchange related to development, design, construction and operation of nuclear power plants with Fast Reactors (FR), as well as to R&D on Accelerator Driven Systems (ADS) Organize Large Conferences on different aspects of FR and ADS RTD Establish a forum for broad exchanges on technical requirements for and characteristics of 4 th Generation Fast Reactor Systems, also in collaboration with INPRO and GIF 3

4 Main activities of the Programme on Fast Neutron Systems (2/2) Carry out Collaborative Research Projects (CRPs) of common interest to the TWG-FR Member States in the field of FRs and ADS Secure Training and Education in the field of fast neutron system physics, technology and applications Support Fast Reactor data retrieval and knowledge preservation activities in MSs Provide support to Nuclear Safety and Security Department for preparation of fast reactor Safety standards / requirements / guides / codes 4

5 The Technical Working Group on Fast Reactors Members of the Technical Working Group on Fast Reactors Members of the Technical Working Group on Fast Reactors Belarus China Germany Italy Kazakhstan Netherlands Switzerland UK OECD/NEA Argentina Spain Full Members Brazil France India Japan Korea, republic of Russian Federation Ukraine USA European Commission Observers Belgium Sweden Full Members Observers Participants in the 44 th Annual Meeting of the TWG-FR, Institute of Atomic Energy (CIAE), Beijing, China, May

6 CRPs Recently Completed 6

7 CRP on Analytical and Experimental Benchmark Analyses of Accelerator Driven Systems (ADS) Advance efforts towards designing a demonstration facility by providing information exchange and collaborative research framework CRP on Analytical and Experimental Benchmark Analyses of Accelerator Driven Systems (ADS) Argentina Belarus Brazil China Poland Russian Federation Belgium France Germany Participants Hungary Italy Japan Netherlands Pakistan Spain Sweden Ukraine USA Improve the present understanding of the coupling of ADS spallation sources with multiplicative sub-critical nuclear system 7

8 CRP on Analyses of, and Lessons Learned from the Operational Experience with Fast Reactor Equipment and Systems Analyses of and lessons learned from the operational experience with fast reactor equipment and systems Participants France Japan India Korea, Republic of Russian Federation Preserve the feedback from commissioning, operation, and decommissioning experience of experimental and power sodium cooled fast reactors Retrieve, assess, review and archive of all the relevant documentation and information Enable easy access to the information from this feedback Produce lessons-learned, synthesis reports of lessons learned and recommendations from the commissioning, operation, and decommissioning of experimental and power sodium cooled fast reactors

9 CRP on Control Rod Withdrawal and Sodium Natural Circulation Tests Performed During the PHENIX End-of-Life Tests Control Rod Withdrawal and Sodium Natural Circulation Tests Performed during the PHENIX End-of-Life Experiments Participants China India Korea, Republic of Switzerland France Japan Russian Federation USA Experimental benchmark exercises (preparatory analyses, blind calculations, and postexperiment analyses) based on the data obtained during the PHENIX End-of-Life tests V&V of methods and codes currently employed in the field of FR neutronics, thermal hydraulics and plant dynamics to achieve enhanced safety

10 CP in Cooperation with INPRO: Integrated Approach for the Modelling of Safety Grade Decay Heat Removal System for LMR INPRO Collaborative Project: Integrated Approach for the Modelling of Safety Grade Decay Heat Removal System for Liquid Metal Reactors" Participants China India Russian Federation EU/JRC Korea, Republic of Reference Design: 500 MWe pool type PFBR Detailed analysis of a DHR system using different codes and modelling approaches to inter-compare the results obtained (7 case studies for different conditions)

11 CRPs to be Completed and to be Launched 11

12 CRP on Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the MONJU Reactor Vessel Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the MONJU Reactor Vessel Participants China India Korea, Republic of USA France Japan Russian Federation Validation of CFD methods and turbulence models based on Na thermal stratification measurements performed in MONJU during a reactor turbine trip test conducted in December 1995 in the course of the original start-up experiments Thorough assessment of the calculation versus measured data comparisons

13 New CRP on Benchmark Analysis of an EBR-II Shutdown Heat Removal Test (to be launched in 2012) Benchmark Analyses of an EBR-II Shutdown Heat Removal Test Expression of Interest China Italy Japan Netherlands Sweden Germany India Korea, republic of Russian Federation Switzerland USA A comprehensive testing program (45 tests!) conducted between 1984 and 1987 A unique set of whole-plant safety tests that demonstrated the potential for SFR to survive severe accident initiators with no damage Two EBR-II loss of flow tests chosen for this CRP: SHRT-17, the most severe of the loss of flow with scram tests SHRT-45, the most severe of the loss of flow without scram tests

14 New CRP on SFR: Sodium Properties, Sodium Facility Design and Safety Guidelines (to be launched in ) This CRP is proposed by France and it is intended to address the needs of standardization of Na physical and chemical properties, the main rules for designing experimental facilities, good practices and safety guidelines The CRP making available validated data and correlations for Na coolant - will also improve the modelling and simulation capabilities in various fields of SFR technology The outputs of this CRP will contribute to an improvement of the future benchmark exercises and of the design of sodium facilities and their safe operation. 14

15 New CRP on Source Term for Radioactivity Release under FR Core Disruptive Accident (CDA) Conditions (to be launched in 2013)?????? Reference design for the safety analysis: 500 MWe pool type PFBR Demonstrate through numerical simulations of FPs transport mechanisms that in future FBRs the radioactivity release to the environment is very low even in the extreme case of CDA Under whole core accident, the fission products and radioactive sodium are the basic source for the radioactivity release

16 Conferences, Workshops & Technical Meetings 16

17 Major Conferences FR09 International Conference on Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, Kyoto, 7-11 December 2009 AccApp'11 - International Conference on Nuclear Research Applications and Utilization of Accelerators, Oak Ridge, Tennessee, USA, 3-7 April

18 Major Conferences FR13 International Conference on Fast Reactors and Related Fuel Cycles - Paris, 3 7 March 2013 (co-organized with Nuclear Fuel Cycle Section and CEA/SFEN-France) AccApp 13 - International Conference on Nuclear Research Applications and Utilization of Accelerators, Ghent, Belgium, USA, July

19 Technical Meetings & Workshops TM on Fast Reactor Physics and Technologies, Kalpakkam, November 2011 GIF-/INPRO Workshop on Safety Aspects of Sodium Fast Reactors, Vienna, 30 Nov. 1 Dec TM (in cooperation with NKM Unit) on the s Fast Reactor Data Retrieval and Knowledge Preservation Initiative, Vienna, 6-8 December 2011 TM on Fast Reactors In-service Inspection and Repair: Status and Innovative Solutions, Vienna, December 2011 TM on Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors, Vienna, December

20 Technical Meetings & Workshops TM on Innovative Fast Reactor Designs with Enhanced Negative Reactivity Feedback Effects, Vienna, February 2012 TM to Identify Innovative Fast Neutron Systems Development Gaps, Vienna, 29 February 2 March 2012 GIF-INPRO Interface Meeting, Vienna, 6 7 March 2012 TM on Impact of Fukushima event on current and future FR designs, Dresden, March JAEA Workshop on Safety of SFR, Tsuruga, Japan, June

21 Technical Meetings & Workshops Fourth Research Coordination Meeting of the CRP on "Benchmark analyses of sodium natural convection in the upper plenum of the MONJU reactor vessel, Tsuruga, Japan, April 2012 First Research Coordination Meeting of the CRP on "Analyses of Fast Reactor Safety Tests Conducted in EBR-II, Argonne, USA, June, th TWG-FR Annual TM, Argonne, June 2012 TM on Construction & Commissioning of SFR, Kalpakkam, India, November

22 Main Deliverables 22

23 Technical Reports closed to Publication Status of Fast Reactor Research and Technology Development (in print) Liquid metal coolants for Fast Reactors: reactors cooled by sodium, lead and lead-bismuth eutectic (in print) Design Features and Operating Experiences of Experimental Fast Reactors (in print) Proceedings of FR09, Kyoto, December 2009 (in print) BN-600 Hybrid Core Benchmark Analysis (under final review by the CRP participants) 23

24 Technical Reports and NES in Preparation BN-600 Hybrid Core Benchmark Analysis: methods to reduce calculation uncertainties of the LMFR reactivity effects (under final editing) Status Report of Accelerator Driven Systems for waste transmutation and energy production (under final editing) Special issue of Nuclear Engineering & Design Journal devoted to the outcomes of the TM on Physics and Technology of Fast Reactors (papers available and under review) 24

25 Technical Reports and NES in Preparation Final Report of the CRP on Analytical and Experimental Benchmark Analyses of Accelerator Driven System Final Report of the CRP on Lessons Learned from the Operational Experience on Fast Reactors (editing just started) Final Reports of the CRP on Control Rod Withdrawal and Sodium Natural Circulation Tests Performed During the PHENIX End-of-Life Tests (first report under review) Final Report of the CRP on Benchmark Analyses of Sodium Natural Convection in the Upper Plenum of the MONJU Reactor Vessel 25

26 FR Project WEB-site: 26

27 TWG-FR WEB-site 27

28 Fast Reactor Knowledge Preservation: FR Data Base Efforts to preserve knowledge and past experience gathered in the operation of fast reactors and FR and ADS R&D programmes Fast Reactor and ADS Data Bases jointly managed by NPTDS/FR Project and Nuclear Knowledge Management (NKM) Unit

29 FRs Knowledge Preservation: FR-KOS System NKM Unit developed a Fast Reactor Knowledge Organization System (FR- KOS): IT system to retrieve information stored in an international data base The NPTDS/FR Project collaborates with the NKM Unit to update the system and collect data and info to be uploaded into the system First version released to MSs for testing and stimulating contributions to FR-KOS 29

30 Objectives of this Meeting 30

31 FRs Experience (mostly SFR) First electricity produced in fast reactor EBR-1 in 1951 Experimental, Demonstrative and power fast reactors have been designed, constructed and operated in several countries About 400 reactors.year of operation experience 31

32 SFR in operation JOYO (suspended) Japan FBTR India BOR-60 Russian Federation CEFR China BN-600 Russian Federation MONJU (suspended) Japan

33 SFR - Under Construction PFBR in India BN-800 in Russian Federation

34 Fast Reactors in a closed fuel cycle: Towards a more sustainable nuclear energy Today s generation of reactors: Safe, reliable and competitive Availability of secure resources (about 100 y at the present rate of consumption) Reprocessing of spent fuel for enhanced use of resources Technical solution for waste management Tomorrow s generation of reactors / Fast Neutron Reactors: The above and. Multiplication by a factor 50 to 100 the energy produced by a given amount of uranium, Minimization of volume, thermal load and radiotoxicity of waste Closing the fuel cycle : enough resources for thousands of years and reduced burden of nuclear waste

35 Large-size Fast Reactors under Development KALIMER, Korea Republic of, 600 MWe BN-1200, Russian Federation, 1200 MWe JSFR, Japan, 1500 MWe CFR, China, 1000 MWe

36 DEMO and PROTO Fast Reactors under Development ASTRID, France, 600 MWe ALFRED, EU, 100 MWe ALLEGRO, France, 100 MWth CFBR, India, 500 MWe

37 Small Modular Fast Reactors under Development PRISM, USA, 155 MWe 4S, Japan, 10 MWe SVBR, Russian Federation, 100 MWe BREST, Russian Federation, 300 MWe HYPERION, USA, 25 MWe SSTAR, USA, MWe TerraPower TWR, USA, 500 MWe

38 Key Elements for FR Development Driving force and peculiarity is sustainability: Natural resources Waste minimization but maintaining/improving Safety (also in light of Fukushima accident) Economical competitiveness Proliferation Resistance Identify technological gaps to achieve the objectives in that areas represents a key step for future developments 38

39 Key Elements for FR Development Innovation to ensure that enhanced requirements for performance, safety and costs are met research and technology development Clear path from research and technology development to deployment Limited resources (economic/financial crisis + industrial and governmental focus on existing and near-term deployment reactors): need to optimize human and financial resources collaboration 39

40 Technical Areas for R&D and Innovation Advanced structural materials Innovative fuels (including MA-bearing fuels) Core performance Primary and secondary system simplification Compact Heat Exchangers New Power Conversion Systems Advanced instrumentation In-service Inspection Safety (reactivity effects, passive systems, etc.) & Security 40

41 Technical Areas for R&D and Innovation Advanced Simulation & Modelling (e.g. multi-physics and multiscale computer codes) with higher level of precision, key for: design optimization (e.g. reduce nominal pick temperatures); drastically reducing uncertainty margins; narrowing down the needs of expensive experimental tests (mock-ups, T/H and safety experiments, etc.) Data and computer code verification, validation, and qualification (V&V&Q) through theoretical and experimental benchmarks, including severe accident analyses Comparative assessments of feasibility, performance, and safety characteristics Technological choices / concept selection 41

42 Objectives of this Technical Meeting Present and discuss new trends in the development of innovative fast neutron systems, with special emphasis on sustainability, economic competitiveness, enhanced safety and nonproliferation Identify gaps between existing reactor technologies and new generation fast neutron systems Identify needs and propose R&D activities to be carried out at international level 42

43 A Key Issue for Innovative FR Development Condition for fast reactor R&D&D is availability of fast neutron experimental (irradiation) facilities. Two concrete projects: MBIR (Russian Federation) MYRRHA by SCK.CEN (Belgium) 43

44 Thanks for Your Attention! Atoms for Peace 44