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Journal Articles

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.*

Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Next Generation Nuclear Systems for Sustainable Development (FR-17) (USB Flash Drive), 15 Pages, 2017/06

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.

Journal Articles

Activities of the safety and operation project for the international research and development of the sodium-cooled fast reactor in the Generation IV international forum

Sakai, Takaaki; Ren, L.*; Tsige-Tamirat, H.*; Vasile, A.*; Kang, S.-H.*; Ashurko, Y.*; Fanning, T.*

Proceedings of 24th International Conference on Nuclear Engineering (ICONE-24) (DVD-ROM), 7 Pages, 2016/06

Journal Articles

Selection of sodium coolant for fast reactors in the US, France and Japan

Sakamoto, Yoshihiko; Garnier, J.-C.*; Rouault, J.*; Grandy, C.*; Fanning, T.*; Hill, R.*; Chikazawa, Yoshitaka; Kotake, Shoji*

Nuclear Engineering and Design, 254, p.194 - 217, 2013/01

 Times Cited Count:16 Percentile:76.68(Nuclear Science & Technology)

This trilateral study confirms that the fundamental mission of the fast reactor is to achieve significant uranium utilization and waste management goals. Thus, fast spectrum reactor concepts are vital for nuclear fuel cycle sustainability goals. The trilateral countries agree that SFR, GFR and LFR are capable to achieve the goals. However SFR is the most matured technology from the view point of industrial deployment while GFR and LFR still require long term development before a test reactor project could begin. The trilateral common view supports fast reactor project situations in each country.

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