超临界水冷堆部分丧失给水瞬态敏感性分析  

Sensitivity Analysis for Transient of Partial Loss of Reactor Coolant Flow of Super LWR

作　　者：罗峰[1] 周涛[1] 程万旭[1] 苏子威[1] 陈娟[1] 

机构地区：[1]华北电力大学核热工安全与标准化研究所,北京102206

出　　处：《核动力工程》2013年第4期100-105,共6页Nuclear Power Engineering

摘　　要：以日本超临界水冷堆(Super LWR)为背景,建立相关数学物理模型,计算分析超临界水冷堆在部分丧失给水瞬态下,主泵惰转时间、紧急停堆延迟时间和密度反馈比对最高包壳温度的影响。分析结果表明:部分丧失给水后,在主泵惰转和反应堆紧急停堆的共同作用下,最高包壳温度先是快速升高,然后快速下降;延长惰转时间能延缓冷却剂流量的减少,从而延缓最高包壳温度的升高;紧急停堆延迟时间越短,越能减缓最高包壳温度的升高;密度反馈比的变化对包壳的温度影响不大。可见,主泵惰转时间、紧急停堆延迟时间能对堆芯的安全性能产生明显的影响。Taking the Super LWR concept proposed by Japanese as the background, relevant mathematical and physical calculation models are built, and the effect of coast-down time of primary pump, scram delay and ratio of density coefficient on the maximum cladding surface temperature （MCST） is evaluated. The results show that： after the transient of partial loss of reactor coolant flow, due to the pump seize and reactor scram, the maximum cladding temperature increases quickly at first and then declines rapidly; extending the coast-down time of primary pump can delay the reduction in the flow of coolant, thereby delaying the increasing of maximum cladding temperature; scram delay is the shorter, thereby better slow down the maximum cladding temperature; Ratio of density coefficient affects the maximum cladding temperature changes a little. Visibly, the coast-down time of primary pump or the scram delay can be a significant impact on the safety performance of the core.

关 键 词：超临界水冷堆 部分丧失给水 敏感性 瞬态 最高包壳温度 

分 类 号：TL364.4[核科学技术—核技术及应用]