摘要
事故工况下辐射防护设计是核电厂辐射防护设计的重要方面,事故后辐射源项作为事故后辐射分区以及人员剂量率评价的重要输入,其计算模型的确定是事故后辐射防护设计中最重要的部分。本文根据设计基准事故放射性后果的严重性,选取大破口失水事故(LOCA)开展事故后辐射防护设计,自主建立事故后气载放射性物质的扩散模型,并验证了源项计算模型的正确性。
Accidents radioprotection plays a significant role in pressurized water reactor radioprotection design. The calculation model of accidents radiation source term, an essential input, is the key process in accidents radioprotection design. According to the severity of DBAs, LOCA is selected as the limiting condition. The method of source calculation is established by analyzing radioactivity release and diffuse model for large LOCA. proved the validity of diffuse model.
出处
《核科学与工程》
CAS
CSCD
北大核心
2015年第4期682-687,共6页
Nuclear Science and Engineering
关键词
大破口失水事故
裂变产物
放射性释放量
Loss of coolant accidents, Fission products,Radioactivity release
