安注方式及停泵时间对船用堆设计基准事故后果的影响分析
Consequence Analysis of Safety Injection Manner and Pump Stopping Time Influence on Design Basic Accident of Marine Reactor
DOI: 10.12677/AEPE.2013.13018, PDF, HTML, XML, 下载: 2,505  浏览: 6,494  国家自然科学基金支持
作者: 张彦招, 张帆, 郑映峰:海军工程大学核能科学与工程系,武汉;段孟强:海军驻431厂代表室,葫芦岛
关键词: 压水堆MELCOR失水事故Pressurized Water Reactor; MELCOR; LOCA
摘要: 本文采MELCOR程序,以某船用压水堆为研究对象,分析了冷却剂主管道冷管段中破口失水事故,将所得结果与该船用堆的安全分析报告进行了比对,验证了MELCOR在计算设计基准事故时的准确性。并针对安注方式、停泵时间对事故后果的影响进行了分析,对预测事故进程、缓解事故后果具有重要意义。
Abstract: In this paper, MELCOR code was applied to analyze the break loss of coolant accident occurring at the cold leg in the main pipe, taking the ship reactor for the object of the research. And the results were compared with the safety analysis report for the ship reactor, which proved the accuracy of the calculation for design basic accident (DBA) by MELCOR. The consequences of the accident was analyzed according to the safety injection manner and the pump stopping time, which is important for predicting the accident progress and alleviating the consequence of the accident.
文章引用:张彦招, 张帆, 段孟强, 郑映峰. 安注方式及停泵时间对船用堆设计基准事故后果的影响分析[J]. 电力与能源进展, 2013, 1(3): 105-108. http://dx.doi.org/10.12677/AEPE.2013.13018

参考文献

[1] 王少明, 章德, 王元, 郝建立. 基于应急运行的核动力装置一回路小破口失水事故[M]. 海军工程大学学报, 2009, 21(4): 55-70.
[2] 朱继洲, 核反应堆安全分析[M]. 西安: 西安交通大学出版社, 2004: 91-101.
[3] 濮继龙, 压水堆核电厂安全与事故对策[M]. 北京: 原子能出版社, 1995: 150-192.
[4] Directorate-General Environment. EUR 19256 EN fuel cladding failure criteria. Brussels: European Com-mission, 1999.
[5] L. Soffer, S. B. Burson, C. M. Ferrell, et al. NUREG-1465, Ac- cident source terms for light-water nuclear power plants. Wash- ington: US Nuclear Regulatory Commission, 1995.
[6] 商学利, 张帆, 陈文振等. 安注方式对设计基准失水事故下元件包壳破损份额影响的分析[J]. 原子能科学技术, 2012, 46(3): 336-340.