应急运行的小破口失水事故过冷度限值分析  

Analysis of the Extreme Degree of Sub-cooling in SBLOCA Based on Emergency Operation

作　　者：秦田夫[1] 项新民 王少明[1] 张龙飞[1] 

机构地区：[1]海军工程大学,武汉430033 [2]海军核安全部,北京100841

出　　处：《船海工程》2011年第2期149-151,155,共4页Ship & Ocean Engineering

摘　　要：利用仿真分析软件对应急工况运行时的船用核反应堆所允许的过冷度限值进行分析,选择不可隔离的小破口失水事故进行分析计算,认为过冷度限值应该为10℃。Utilizing the emulate analysis software,extreme degree of sub-cooling allowed to the marine nuclear reactor operating in the emergency conditions was studied,and SBLOCA that cannot be segregated was chosen to calculate some data.A conclusion was educed that the extreme degree of subcooling should be 10℃.

关 键 词：核动力装置 过冷度 应急运行安全 

分 类 号：U677.3[交通运输工程—船舶及航道工程] TL364.4[交通运输工程—船舶与海洋工程]