中国先进研究堆事故源项分析  

Accident Source Term Analysis in China Advanced Research Reactor

作　　者：黄东兴[1] 浦胜娣[1] 李吉根[1] 

机构地区：[1]中国原子能科学研究院反应堆工程研究设计所,北京102413

出　　处：《原子能科学技术》2005年第5期438-441,共4页Atomic Energy Science and Technology

摘　　要：研究建立了中国先进研究堆(CARR)在事故工况下放射性核素从燃料芯块向环境释放的数学模型。根据CARR初步事故分析结果,对可能导致放射性向外界释放的5种事故工况(小破口失水事故、换热器传热板破裂事故、重水回路管道破裂事故、燃料操作事故、冷却剂流道堵塞事故)以及假想的3盒组件燃料板熔化超设计基准事故进行了源项分析,分别给出了不同事故和释放途径下释放到环境的放射性核素的量,以防止事故情况下公众和环境遭受过量放射性损伤。The mathematics model in which radioactive nuclides are released from nuclear fuel to the environment during accident conditions in China Advanced Research Reactor（CARR） is eatablished. The source terms in the following accidents are analyzed, including small loss of coolant accident, heat exchanger plate break, heavy water loop break, fuel handling accident, coolant channel blocking accident, and three fuel assemblies meltdown. The quantities of radioactive nuclides released to the environment through different paths during accidents to the public during accident conditions. are given to prevent undue radiological hazard

关 键 词：中国先进研究堆 数学模型 事故源项分析 

分 类 号：TL732[核科学技术—辐射防护及环境保护]