| 利用可选择源项分析大破口失水事故的放射性后果 |
| |
| 引用本文： | 黄高峰,佟立丽,邓坚,曹学武.利用可选择源项分析大破口失水事故的放射性后果[J].原子能科学技术,2009,43(8):738-742. |
| |
| 作者姓名： | 黄高峰 佟立丽 邓坚 曹学武 |
| |
| 作者单位： | 上海交通大学 机械与动力工程学院，上海 ;200240 |
| |
| 基金项目： | 国家重点基础研究发展计划资助项目 |
| |
| 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900MW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。
|
| 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 |
| 收稿时间： | 2008-05-22 |
| 修稿时间： | 2008-06-17 |
Radiological Consequences in Large Break Loss of Coolant Accident With Alternative Source Term |
| |
| HUANG Gao-feng,TONG Li-li,DENG Jian,CAO Xue-wu.Radiological Consequences in Large Break Loss of Coolant Accident With Alternative Source Term[J].Atomic Energy Science and Technology,2009,43(8):738-742. |
| |
| Authors: | HUANG Gao-feng TONG Li-li DENG Jian CAO Xue-wu |
| |
| Affiliation: | School of Mechanical and Power Engineering, Shanghai Jiao Tong University, Shanghai 200240, China |
| |
| Abstract: | 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. |
| |
| Keywords: | alternative source term large break loss of coolant accident design base accident radiological consequences |
| 本文献已被 万方数据 等数据库收录！ |
| 点击此处可从《原子能科学技术》浏览原始摘要信息 |
|
点击此处可从《原子能科学技术》下载全文 |
