主泵参数变化对失水事故后果影响分析  

Effect of Parameter Variation of Reactor Coolant Pump on Loss of Coolant Accident Consequence

作　　者：党高健[1] 黄代顺[1] 高颖贤[1] 何晓强[1] 

机构地区：[1]中国核动力研究设计院核反应堆系统设计技术重点实验室,成都610041

出　　处：《核动力工程》2015年第1期132-136,共5页Nuclear Power Engineering

摘　　要：基于100D主泵和ANDRITZ主泵的差异,分析主泵相似特性曲线和自由容积的变化对失水事故(LOCA)后果的影响。针对岭澳核电站二期反应堆冷却剂系统,应用CATHARE GB程序和CONPATE4程序分析大破口LOCA事故堆芯热工水力后果;应用ATHIS和FORCET程序分析失水事故喷放阶段的反应堆冷却剂主管道水力载荷。结果表明,主泵相似特性曲线的变化对大LOCA事故再淹没阶段的堆芯热工特性影响很大,采用不同主泵时的最高峰值包壳温度(PCT)相差很大;而主泵自由容积对失水事故喷放阶段的卸压波传递影响较大,导致采用不同主泵时的反应堆冷却剂主管道水力载荷有所不同。In this paper, the analyses were carried out on Ling＇ao nuclear power station phase Ⅱ to study the consequence of the loss of coolant accident when the homologous characteristic curves and free volumes of the reactor coolant pump changed. Two different pumps used in the analysis were 100D （employed on Ling＇ao nuclear power station phaseII） and ANDRITZ. The thermal characteristics in the large break LOCA accident were analyzed using CATHRE GB and CONPATE4, and the reactor coolant system hydraulics load during blow-down phase of LOCA accident was analyzed using ATHIS and FORCET. The calculated results show that the homologous characteristic curves have great effect on the thermal characteristics of reactor core during the reflood phase of the large break LOCA accident. The maximum cladding surface temperatures are quite different when the pump＇s homologous characteristic curves change. On the other hand, the pump＇s free volume changing results in the variation of the LOCA rarefaction wave propagation, and therefore, the reactor coolant system hydraulic load in LOCA accident would be different.

关 键 词：相似特性曲线 自由容积 失水事故 峰值包壳温度 水力载荷 

分 类 号：TL364.4[核科学技术—核技术及应用]