摘要
研制了反应堆维修期间堆芯自然散热的计算分析程序,并对程序计算结果和跟踪试验结果进行了比较,表明了本程序的计算结果是正确可靠的,为掌握堆芯无冷却时冷却剂压力和温度等参数的变化规律提供了有力的计算工具,对确保维修期间的核安全提供了科学可靠的技术依据。
An analysis code of thermal-hydraulic parameters is developed for calculating natural radiating heat during reactor maintenance. The calculating results and experiment results are compared and it shows that the calculated results are precise and reliable. The code is a very important tool for obtaining the rule of thermal hydraulic parameters when the core cooling ability is lost, and provides scientific and reliable technical basis for nuclear safety during maintenance.
出处
《核科学与工程》
CSCD
北大核心
2008年第2期163-166,共4页
Nuclear Science and Engineering
关键词
反应堆
维修
核安全
冷却剂
自然散热
reactor
maintenance
nuclear safety
coolant
natural radiating heat
