Recent activities of the safety and operation project of the sodium-cooled fast reactor in the Generation IV International Forum

Vasile, A.*; Ren, L.*; Fanning, T.*; Tsige-Tamirat, H.*; Yamano, Hidemasa ; Kang, S.-H.*; Ashurko, I.*

The tasks in the Safety and Operation (SO) topics are categorized into the following three work packages (WP): WP-SO-1 Methods, Models and codes is devoted to the development of tools for the evaluation of safety, WP-SO-2 Experimental Programs and Operational Experiences includes the operation, maintenance and testing experiences in experimental facilities and SFRs (e.g., Monju, Phenix, BN-600 and CEFR), and WP-SO-3 Studies of Innovative Design and Safety Systems relates to safety technologies for GEN-IV reactors such as active and passive safety systems and other specific design features. In this paper, recent activities in the SO project are described.

Language	:	English
Journal	:	Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive)
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Pages	:	15 Pages
Publication Year/Month	:	2017/06
Meeting title	:	International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17)
Held date	:	2017/06
Location (city)	:	Yekaterinburg
Location (country)	:	Russia
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DOI for research data	:
Keywords	:	Sodium-Cooled Fast Reactor; Generation IV; Safety and Operation
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Article of JAEA R&D Review	:
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Registration No. : BB20170462
JAEA Abstracts No. : 45000948
Paper Submission No. : 19192

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