| DVI管小破口失水事故实验研究 |
| |
| 引用本文： | 彭传新,张妍,黄志刚,昝元锋,卓文彬,闫晓.DVI管小破口失水事故实验研究[J].原子能科学技术,2016,50(10):1787-1792. |
| |
| 作者姓名： | 彭传新 张妍 黄志刚 昝元锋 卓文彬 闫晓 |
| |
| 作者单位： | 中国核动力研究设计院 中核核反应堆热工水力技术重点实验室，四川 成都610041 |
| |
| 基金项目： | 国家杰出青年科学基金资助项目(11325526)；863计划资助项目(2012AA050906) |
| |
| 摘 要： | 在模块化小型反应堆非能动安全系统综合模拟实验装置上进行了压力容器直接注入（DVI）管小破口失水事故实验，研究了DVI管小破口失水事故过程中的热工水力现象和非能动安全系统运行特性。研究结果表明：模块化小型反应堆DVI管小破口失水事故中，非能动安全系统可对堆芯进行注水，有效导出堆芯衰变热量，保护堆芯安全。
|
| 关 键 词： | 小破口失水事故 DVI管 非能动安全系统 |
Experimental Investigation on Small Break Loss of Coolant Accident for Direct Vessel Injection Line |
| |
| PENG Chuan-xin,ZHANG Yan,HUANG Zhi-gang,ZAN Yuan-feng,ZHUO Wen-bin,YAN Xiao.Experimental Investigation on Small Break Loss of Coolant Accident for Direct Vessel Injection Line[J].Atomic Energy Science and Technology,2016,50(10):1787-1792. |
| |
| Authors: | PENG Chuan-xin ZHANG Yan HUANG Zhi-gang ZAN Yuan-feng ZHUO Wen-bin YAN Xiao |
| |
| Affiliation: | CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu 610041, China |
| |
| Abstract: | T he small break loss of coolant accident (SBLOCA ) experiment for direct vessel injection (DVI ) line , w hich investigated the thermal‐hydraulic phenomena and the performances of passive safety system during the accident ,was performed on the passive safety system test facility for small modular reactor .The experimental results show that the passive safety system of small modular reactor can provide effective cool‐ant injection ,successful removal of core residual heat under the DVI line SBLOCA and protection to reactor core safety . |
| |
| Keywords: | small break loss of coolant accident DVI line passive safety system |
| 本文献已被 CNKI 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 |
