Thermal Response of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors. International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource.

Zhang, H. ; Zhao, H. ; Davis, C. B.

Technical Information Center Oak Ridge Tennessee

关键词: Nuclear reactors;    Meetings;    Fast reactors;    Shutdown;    Sodium;   

RP-ID  :  DE2008941748

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

An innovative hybrid loop-pool design for the sodium cooled fast reactor (SFR) has been recently proposed with the primary objective of achieving cost reduction and safety enhancement. With the hybrid loop-pool design, closed primary loops are immersed in a secondary buffer tank. This design takes advantage of features from conventional both pool and loop designs to further improve economics and safety. This paper will briefly introduce the hybrid loop-pool design concept and present the calculated thermal responses for unproctected (without reactor scram) loss of forced circulation (ULOF) transients using RELAP5-3D. The analyses examine both the inherent reactivity shutdown capability and decay heat removal performance by passive safety systems.