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严重事故下反应堆压力容器外水冷有效性概率分析
引用本文:曹克美,许以全,史国宝,蔡剑平.严重事故下反应堆压力容器外水冷有效性概率分析[J].核动力工程,2009,30(1).
作者姓名:曹克美  许以全  史国宝  蔡剑平
作者单位:上海核工程研究设计院,上海,200233
摘    要:核反应堆的严重事故现象具有较大不确定性,它们影响到反应堆压力容器外水冷措施的有效性.本文应用风险导向事故分析方法,分析了堆芯熔融物在压力容器内滞留的不确定性,得到了反应堆压力容器外水冷有效性的概率分布.用VTA抽样程序的计算结果表明,在发生假想的严重事故并成功实施反应堆压力容器外水冷措施后,对于分析的8类严重事敝序列,若下封头熔融池达到最终包络状态,恰希玛-2核电厂实现堆芯熔融物在压力容器内滞留的成功概率超过99%.

关 键 词:严重事故  压力容器外水冷  堆芯熔融物  压力容器内滞留  恰希玛核电厂

Probability Analysis for External Reactor Vessel Cooling Effectiveness under Severe Accident
CAO Ke-mei,XU Yi-quan,SHI Guo-bao,CAI Jian-ping.Probability Analysis for External Reactor Vessel Cooling Effectiveness under Severe Accident[J].Nuclear Power Engineering,2009,30(1).
Authors:CAO Ke-mei  XU Yi-quan  SHI Guo-bao  CAI Jian-ping
Affiliation:Shanghai Nuclear Engineering Research and Design Institute;Shanghai;200233;China
Abstract:There are many uncertainties in severe accident phenomena which affect the effectiveness of External Reactor Vessel Cooling (ERVC) measurement. The uncertainties of In-Vessel Retention (IVR) issue are analyzed based on Risk-Oriented Accident Analysis method, and the probability distribution of ERVC effectiveness is obtained. The calculation results using VTA sampling program show that if the melt pool in lower head achieves final bounding state, the success probability of core debris IVR is over 99% for 8 k...
Keywords:Severe accident  External reactor vessel cooling  Core debris  In-vessel retention  Chashma nuclear power plant  
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