Heating and Cooling mode Supercritical CO2 Heat Transfer
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.
heat transfer supercritical CO2 CFD heat exchanger
Alan Kruizenga Hongzhi Li Mark Anderson
University of Wisconsin 1500 Engineering Drive Madison WI 53706 University of Wisconsin 1500 Engineering Drive Madison WI 53706；Xi’an Jiaotong University State Key
国际会议
上海
英文
1315-1326
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）