Nuclear Power Technology Development
IAEA, Vienna, Austria
3rd Joint GIF-IAEA Workshop on Safety Design Criteria for Sodium-Cooled Fast Reactors
The Generation IV International Forum (GIF), and the IAEA are collaborating and sharing information in selected areas, including the safety of Sodium-cooled Fast Reactors (SFR) and in particular the harmonization of safety approach, safety requirements and safety design criteria for the GENIV SFRs under development worldwide.
In this workshop, GIF, the IAEA (through the Department of Nuclear Energy and the Department of Safety and Security), and Member States will present and share information on safety design criteria for SFR, including safety approach and requirements for general plant design.
This page contains the most up-to-date information and materials regarding the event. Please visit this page regularly, as new and revised materials will be uploaded here as they become available.
Working Documents
Presentations
Day 1
Opening Remarks
J.K. Park, Director, IAEA Division of Nuclear PowerOpening Remarks
Y. Sagayama, Vice-Chair, GIFSafety Design Criteria (SDC) for Gen-IV Sodium-cooled Fast Reactor
Nakai, GIF SDC Task Force ChairSafety Requirements / Design Criteria for SFR Lessons Learned from the Fukushima Dai-ichi Accident
J. Yllera, IAEA/NSNISafety Design Criteria of Indian Sodium Cooled Fast Reactors
P. Pillai, IGCAR, Kalpakkam, IndiaEuropean project SARGEN_IV: safety approach and assessment of GEN IV reactors
L. Ammirabile, EC JRC-IET Institute for Energy and Transport, Petten - The NetherlandsANS 54.1 - Nuclear Safety Criteria and Design Process for Liquid–Sodium–Cooled–Reactor Nuclear Power Plants
G. F. Flanagan, Oak Ridge National Laboratory, USASafety Design Approach based on Gen-IV SFR SDC
S. Kubo, GIF SDC Task Force
Day 2
SFR Specific Criteria
Y. Okano, GIF SDC-TF memberSafety features designed to eliminate the need for off-site emergency response
Liu Yizhe, CIAE, ChinaProposal of safety orientations for Generation 4 SFRs
P. Anzieu, CEA, FranceSevere accidents and ESFR design issues
A. Rineiski, KIT, GermanyDesign Extension in Post Fukushima Scenario
P. Kumar, Department of Atomic Energy of India, IndiaSafety design approach for JSFR toward the realization of GEN IV SFR
S. Kubo, JAEA, JapanSafety Approach of PGSFR in Korea
Hae-Yong JEONG, KAERI, Republic of KoreaBN-1200 Safety Concept
Y. Ashurko, IPPE, Russian FederationAn Overview and Evaluation of U.S. SFR Safety Approach
Tanju Sofu, ANL, USA
Scientific Secretaries
Mr. S. Monti
Nuclear Power Technology Development Section
IAEA Division of Nuclear Power
Mr. J. Phillips
INPRO Group
IAEA Division of Nuclear Power
