10th GIF-IAEA/INPRO Interface Meeting. IAEA Headquarters, Vienna April Fast Reactor Programme. IAEA International Atomic Energy Agency

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1 10th GIF-/INPRO Interface Meeting Headquarters, Vienna April 2016 Fast Reactor Programme Vladimir Kriventsev, Stefano Monti Fast Reactor Technology Development Team Nuclear Power Technology Development Section Department of Nuclear Energy International Atomic Energy Agency

2 Outline TWG-FR: Technical Working Group on Fast Reactors Programmatic Approach: Modeling & Simulations Technical Support FR Safety Information Exchange Education & Training Knowledge Preservation International Conferences on Fast Reactors Recent Achievements / on-going activities Major Planned Outputs 2

3 The Technical Working Group on Fast Reactors (TWG-FR) TWG advices to define the Programmatic Content 48 th Annual Meeting of the TWG-FR IPPE, Obninsk, Russia May 2015 Members of the Technical Working Group on Fast Reactors Full Members Belarus Brazil China France Germany India Italy Japan Kazakhstan Korea, republic of Netherlands Russian Federation Slovakia Sweden Switzerland Ukraine UK USA European Commission OECD/NEA Observers Argentina Belgium Czech Republic Mexico Romania Spain Generation-IV International Forum (GIF) 49 th Annual Meeting of the TWG-FR CNEA, Buenos Aires, Argentina May

4 Programmatic Areas: Fast Reactors Technology Support Modelling and Simulations Fast Reactors Knowledge Preservation Safety Education & Training

5 Recent FR Achievements CRPs: Completed: MONJU, PHENIX EOL, ADS Ongoing: NAPRO, EBR-II Just Started: PFBR-ST In Plans: MONJU-TTT, FFTF, CEFR Education and Training: Publications:

6 Major Planned Outputs FR 17 Conference FRKP portal SFR Simulator EBR- II Benchmark Results Handbook on Sodium Properties

7 International Conference on Fast Reactors and Related Fuel Cycles The International Conference on Fast Reactors and Related Fuel Cycle represents the most important event on fast reactors and related fuel cycles technology FR09 in Kyoto, Japan, 2009 FR13 in Paris, France, 2013 FR17 in Yekaterinburg, Russian Federation, May-June 2017

8 EBR-II CRP: Benchmark Analyses of the Shutdown Heat Removal Tests Performed in the EBR-II Reactor A very productive verification and validation exercise accomplished. 20 Organizations from 12 countries Final RCM of the CRP : April 2016 Compilation of final simulation results and produce consolidated document in one year

9 NAPRO CRP: Sodium properties and safe operation of experimental facilities in support of the development and deployment of SFR Sodium properties and safe operation of experimental facilities in support of the development and deployment of SFR Argentina (CNEA) France (CEA) Germany (KIT, HZDR) Korea, Republic of (KAERI) Russian Federation (IPPE) China (CIAE) India (IGCAR) Japan (JAEA) Netherlands (NRG) USA (ANL) WP1: Collection and assessment of sodium properties: international harmonization of data and correlations to be published in the form of a handbook WP2: Design rules and best practice for Na exp. facilities WP3: Guidelines for the safe operation of Na exp. facilities 3 rd RCM at CEA-Cadarache, France, 5-9 October th RCM in Vienna, 1 st Q 2017 First draft of Na Handbook (WP1): to be published in

10 Fast Reactor Knowledge Organization System DATA, INFORMATION AND KNOW- HOW HOLDERS

11 E&T: Development of SFR Simulator for Educational Purposes Funded by RB + MEXT-Japan + in-kind contributions from other interested MSs 1 st CM to finalize specs: January 2016 Final Detailed Technical Specifications prepared by : ready by April 2016

12 E&T: Joint -ICTP Workshop on Physics and Technology of Innovative Nuclear Energy Systems for Sustainable Development 29 th August 2 nd September 2016 Trieste, Italy

13 GIF- Workshop(s) on Safety of SFR 2011-Present 2 nd GIF- Workshop on Safety of SFR: rd GIF- Workshop on Safety of SFR: Feb th GIF- Workshop on Safety of SFR: June th GIF- Workshop on Safety of SFR: June th GIF- Workshop on Safety of SFR: November 2016 (proposed) 13

14 CRP on Radioactive Release from the Indian Prototype Fast Breeder Reactor (PFBR) under Severe Accident Conditions CRP on Radioactive Release from the PFBR under Severe Accident Conditions Expressions of Interest Canada, UOIT France, IRSN & CEA India, IGCAR Russian Federation, IPPE China, CIAE, NCEPU Germany, KIT Korea, Republic of, KAERI EC-JRC i. 0 ms ii. 50 ms iii. 100 ms iv. 150 ms v. 200 ms Numerical simulation of core bubble expansions during a CDA (100 MJ) Reference design for the safety analysis: 500 MWe pool type PFBR Evaluation of: Transport of fission products (FP), Na and other radioactive materials from the melted core to the cover gas Ejection of FP, Na, fuel particles through the penetrations of the top shield reactor structure directly into the containment system and indirectly through the argon cover gas system Transport of fission products and other radioactive materials through the different containment compartments under various thermodynamics conditions First RCM: Vienna, 3-6 May 2016

15 Compendium of Experimental Facilities in support of SFR and LFR 150 facilities 14 countries

16 Conclusions Fast reactors technology has been brought to a high level of technical maturity in the last decades by the design, construction and operation of experimental and prototype reactors, and a number of construction projects are currently on going Several countries are engaged in the development of innovative (GEN-IV) FR concepts: SFR, LFR, GFR, MSFR Important research efforts are worldwide devoted to cover technology gaps and improve safety features, especially in the light of the Fukushima event In order to promote cooperation, international initiatives have been established in last years: GIF, INPRO, ESNII The supports Member States activities by providing a forum for information exchange and implementing R&D programmes 16

17 Thanks for Your Attention! Atoms for Peace & Development 17

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