Seventh Joint IAEA–GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors

One of the key areas of collaboration between the Generation IV International Forum (GIF) and the IAEA is the safety of sodium cooled fast reactors (SFRs) and, in particular, the harmonization of safety approaches, safety requirements, Safety Design Criteria (SDC) and Safety Design Guidelines (SDG) for the next-generation SFRs under development worldwide. Six joint IAEA–GIF Technical Meetings/Workshops on the safety of SFRs have been held since 2010.

The 7th Joint IAEA-GIF Technical Meeting/Workshop on the Safety of Liquid Metal Cooled Fast Reactors will:

• Discuss the final version of the GIF report entitled Safety Design Guidelines on Safety Approach and Design Conditions for Generation IV Sodium-cooled Fast Reactor Systems;
• Share information on the implementation of SDG for SFRs by the designers of innovative SFR concepts; and
• Discuss the development of the draft GIF report provisionally entitled Safety Design Guidelines on Key Structures, Systems and Components

Presentations

Session I: Updated SFR SDC/SDG and related activities

• Safety Design Guidelines (SDG) on Safety Approach and Design Conditions for Generation-IV Sodium-cooled Fast Reactor System, S. Kubo, GIF SDC Task Force
• Up-to-Date Development Status of ?Structures, Systems and Components Safety Design Guidelines (SSC-SDG), Y. Okano, GIF
• Comments on Guidelines for SFR Safety Approach and Design Conditions, T. Sofu, Argonne National Laboratory, USA, and GIF

Session II: Licensing framework for advanced reactors and related activities

• U.S. Nuclear Regulatory Commission’s Non-Light Water Reactor Licensing Activities, J. Mazza, U.S. NRC
• Containment and Sodium-specific SFR Design Criteria in RG 1.232, I.K. Madni, U.S. NRC
• Overview of Safety R&D in the Horizon-2020 ESFR-SMART Project,?H. Tsige-Tamirat, European Commission Joint Research Center?
• New Safety Measures Propositions for European Sodium Fast Reactor in Horizon-2020 ESFR-SMART Project, J.?Guidez, CEA, France
• Practical Elimination Approach for Gen-IV Reactors, J. Guidez, CEA, and Chair of GCFS?
• Design?evolution?of?Japanese?Generation‐Ⅳ SFR?based?on?the?GIF?SDC?and?SDG, K. Higurashi, MFBR, Japan
• Implementation of Safety Design Criteria in the Large Power Size Sodium Cooled Fast Reactor BN-1200 Design, Y. Ashurko, IPPE, Russian Federation
• IAEA Activities on LMFR Technology and FR17 Panel Discussion on SFR SDC/SDG, V. Kriventsev,?IAEA/NPTDS
• Digital Nuclear Reactor Data Storage Toolkit, C. Chirayu, IAEA/NPTDS

Session III: Implementation of SDC/SDG by Designers of Innovtive SFR Concepts

• Safety Approach for PGSFR Specific Design,?Seok-Hun Kang, KAERI
• Safety Design Criteria of Indian Sodium Cooled Fast Reactors: Current Status, P. Pillai, IGCAR, India

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All presentations are available in the IAEA INIS Database

(reportnumber?:"INIS-XA--18M2236")