Development of Level 2 PSA Methodology for Sodium-Cooled Fast Reactors (5) Development of Technical Basis for the Protected Loss of Heat Sink
(0) As part of level-2 PSA methodology development for sodium cooled fast reactors, the phenomenological event tree for the Protected Loss of Heat Sink (PLOHS) is constructed for JSFR (Japan Sodium Fast Reactor). The early stage of PLOHS accident, where the heating of coolant, coolant boiling and uncovering of core occurs, is analyzed by ARGO code. The event progression in the sub-sequent core disruption phase, where the meltdown of core and the power transient by re-criticality occurs, is analyzed by APPLOHS and SIMMER-III codes. The dominant factors, which affect the event progression in PLOHS, are recognized through these analyses and by considering the phenomenological event progression based on the preceding study1. The event tree of PLOHS is developed assigning these dominant factors as the headings. For each of the headings, available information for judgment of branching probability are reviewed and integrated as database for level-2 PSA.
FBR Level 2 PSA LOHRS PLOHS event tree database
Yoshiharu Tobita Hidemasa Yamano
Japan Atomic Energy Agency 4002 Narita-cho, O-arai, Ibaraki, 311-1393, Japan
国际会议
上海
英文
1304-1314
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）