Title: Status of the Advanced Fuel Project for Sodium-Cooled Fast Reactor as a Generation IV Nuclear Energy System
Citation: Proceedings of the International Conference Nuclear Energy System for Future Generation and Global Sustainability (GLOBAL 2005) p. Paper No. 447
Publisher: Atomic Energy Society of Japan (AESJ)
Publication Year: 2005
JRC N°: JRC30598
URI: http://publications.jrc.ec.europa.eu/repository/handle/JRC30598
Type: Articles in periodicals and books
Abstract: The Sodium-cooled Fast Reactor(SFR) is one of the six promising nuclear energy systems for future proposed by the Generation IV International Forum(GIF). Typical concept of advanced fuel considered in SFR system includes high burnup and Minor Actinides(MA) bearing fuel to meet the Generation IV goals. International collaborative plan of advanced fuel development is under discussion in the Advanced Fuel Project Management Board(AFPMB) under the SFR System Steering Committee(SSC) of the GIF framework to start the official collaboration before the end of 2005. The current planning discussion includes the whole "Advanced Fuel" project in which the duration beyond 2015 is considered. As the first milestone, the outcomes of various R&D effort of oxide, metal and nitride fuels will be gathered by the end of 2006 and a comparative evaluation will be made by AFPMB. Further milestones are planned in 2010 and 2015, which lead to the activity of demonstration and application of advanced fuel. By achieving each milestone, the AFPMB will provide one of the concrete solutions for the establishment of SFR Generation IV nuclear energy system.
JRC Directorate:Nuclear Safety and Security

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