A summary of sodium-cooled fast reactor development

Journal Article · Sat Nov 01 00:00:00 EDT 2014 · Progress in Nuclear Energy

DOI:https://doi.org/10.1016/j.pnucene.2014.05.008· OSTI ID:1392913

Aoto, Kazumi; Dufour, Philippe; Hongyi, Yang; Glatz, Jean Paul; Kim, Yeong-il; Ashurko, Yury; Hill, Robert; Uto, Nariaki

Much of the basic technology for the Sodium-cooled fast Reactor (SFR) has been established through long term development experience with former fast reactor programs, and is being confirmed by the Phénix end-of-life tests in France, the restart of Monju in Japan, the lifetime extension of BN-600 in Russia, and the startup of the China Experimental Fast Reactor in China. Planned startup in 2014 for new SFRs: BN-800 in Russia and PFBR in India, will further enhance the confirmation of the SFR basic technology. Nowadays, the SFR development has advanced to aiming at establishment of the Generation-IV system which is dedicated to sustainable energy generation and actinide management, and several advanced SFR concepts are under development such as PRISM, JSFR, ASTRID, PGSFR, BN-1200, and CFR-600. Generation-IV International Forum is an international collaboration framework where various R&D activities are progressing on design of system and component, safety and operation, advanced fuel, and actinide cycle for the Generation-IV SFR development, and will play a beneficial role of promoting them thorough providing an opportunity to share the past experience and the latest data of design and R&D among countries developing SFR.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1392913
• Journal Information: Progress in Nuclear Energy, Vol. 77; ISSN 0149-1970
• Publisher: Elsevier
• Country of Publication: United States
• Language: English