| 应急运行的小破口失水事故过冷度限值分析 |
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| 引用本文： | 秦田夫,项新民,王少明,张龙飞. 应急运行的小破口失水事故过冷度限值分析[J]. 船海工程, 2011, 40(2). DOI: 10.3963/j.issn.1671-7953.2011.02.042 |
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| 作者姓名： | 秦田夫 项新民 王少明 张龙飞 |
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| 作者单位： | 1. 海军工程大学,武汉,430033
2. 海军核安全部,北京,100841 |
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| 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℃.
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| 关 键 词： | 核动力装置 过冷度 应急运行安全 |
Analysis of the Extreme Degree of Sub-cooling in SBLOCA Based on Emergency Operation |
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| QIN Tian-fu,XIANG Xin-min,WANG Shao-ming,ZHANG Long-fei. Analysis of the Extreme Degree of Sub-cooling in SBLOCA Based on Emergency Operation[J]. Ship &Ocean Engineering, 2011, 40(2). DOI: 10.3963/j.issn.1671-7953.2011.02.042 |
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| Authors: | QIN Tian-fu XIANG Xin-min WANG Shao-ming ZHANG Long-fei |
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| Affiliation: | QIN Tian-fu1,XIANG Xin-min2,WANG Shao-ming1,ZHANG Long-fei1(1.Naval University of Engineering,Wuhan 430033,China,2.Naval Nuclear Safety Department,Beijing 100841,China) |
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| Abstract: | |
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| Keywords: | nuclear power plant degree of subcooling emergency operation safety |
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