摘要
利用轻水堆系统通用的热工水力分析程序RETRAN02 , 对200 MW 池式供热堆的未能紧急停堆的预期瞬变(ATWS) 事故, 即断电ATWS 事故、误提棒ATWS 事故、外负荷丧失ATWS 事故等进行了计算和分析。结果表明, 在事故过程中, 主要参数没有超出允许范围; 不需任何设备动作和人员干预, 反应堆就能自动降功率, 进入热停堆状态并维持长期堆芯冷却, 具有较高的安全性。
The thermal hydrodynamic code RETRAN 02 is used for safety analysis of Anticipated Transients Without Scram (ATWS) accidents for the 200MW Deep Pool heating Reactor (DPR) These ATWS accidents are caused by loss of power,loss of load,and unexpected reactivity insertion The calculation results verify that the major parameters are well within the limits defined by safety criteria with sufficient safety margin,and neither extra safety facility nor human intervention is needed during all transients and accidents The reactor (DPR) itself is able to decrease its power and shut down by means of higher coolant temperature,and keep core cooling for a long term The conclusion is that the DPR has high level of inherent passive safety
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1999年第5期428-431,共4页
Nuclear Power Engineering
关键词
池式
供热堆
紧急停堆
预期瞬变事故
堆芯冷却
Pool type heating reactor Anticipated transients without scram Hot shutdown condition Core cooling