利用可选择源项分析大破口失水事故的放射性后果  

Radiological Consequences in Large Break Loss of Coolant Accident With Alternative Source Term

作　　者：黄高峰[1] 佟立丽[1] 邓坚[1] 曹学武[1] 

机构地区：[1]上海交通大学机械与动力工程学院,上海200240

出　　处：《原子能科学技术》2009年第8期738-742,共5页Atomic Energy Science and Technology

基　　金：国家重点基础研究发展计划资助项目(2009CB724301)

摘　　要：阐述了应用可选择源项分析设计基准事故放射性后果的基本方法,并以900 MW核电厂为研究对象,利用一体化安全分析程序分析大破口失水事故的放射性后果,包括主控室、非居住区边界和低人口密度区外边界的剂量计算,并与美国核管会(NRC)管理导则1.183中的剂量准则相比较,结果均在可接受值之内。The method of analysing radiological consequences for design base accident by using alternative source term was described. The radiological consequences were analyzed by using integral safety analyse code for nuclear power plant of 900 MW in the case of large break loss of coolant accident, including dose computation of control room, exclusion area boundary and outer boundary of low population zone. The results were compared wih dose rule of Nuclear Regulary Committee （NRC） Regulary Guide 1. 183 and met the dose criteria.

关 键 词：可选择源项 大破口失水事故 设计基准事故 放射性后果 

分 类 号：TL364.4[核科学技术—核技术及应用]