后处理厂与核电厂概率安全评价方法学的比较

Comparison of probabilistic safety assessment methodologies for nuclear fuel reprocessing and nuclear power plants

为了确保中国动力堆乏燃料后处理中间试验工厂(中试厂 )安全可靠地设计和运行 ,在用确定论方法对其事故进行分析的同时 ,有必要应用概率安全评价 (PSA)方法对中试厂进行安全评价。该文借鉴核电厂 PSA实践经验 ,研究了国际上后处理厂 PSA的应用情况 ,从设计安全基本原则、PSA方法学、可靠性数据、事故辐射后果等方面 ,比较了概率安全评价技术在核电厂与核燃料后处理厂应用中的异同 ,最后确定了后处理厂概率安全评价的具体方法独立的故障树演绎技术 ,并实际应用于中试厂的概率安全评价。结果表明 ,后处理厂比核电厂具有较低的风险和较好的安全性。

The safe design and operation of a reactor spent fuel reprocessing plant needs a probabilistic safety assessment (PSA). The practical experience gained from using PSA for domestic nuclear power plants and from studing PSA methods for foreign nuclear fuel reprocessing plants was used in the study. This paper compares the main design safety principles, PSA methodologies, reliability data and accident radiometic consequences, etc. A specific PSA method for nuclear fuel reprocessing plants, the stand alone fault tree deductive technique is recommended for a safety analysis.