期刊文献+
共找到1篇文章
< 1 >
每页显示 20 50 100
Framework analysis of fluoride salt-cooled high temperature reactor probabilistic safety assessment 被引量:1
1
作者 左嘉旭 靖剑平 +2 位作者 毕金生 宋维 陈堃 《Nuclear Science and Techniques》 SCIE CAS CSCD 2015年第5期112-117,共6页
Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized wat... Probabilistic safety assessment(PSA) is important in nuclear safety review and analysis. Because the design and physics of the fluoride salt-cooled high temperature reactor(FHR) differ greatly from the pressurized water reactor(PWR), the methods and steps of PSA in FHR should be studied. The high-temperature gascooled reactor(HTR-PM) and sodium-cooled fast reactors have built the PSA framework, and the framework to finish the PSA analysis. The FHR is compared with the PWR, HTR-PM and sodium-cooled fast reactors from the physics, design and safety. The PSA framework of FHR is discussed. In the FHR, the fuel and coolant combination provides large thermal margins to fuel damage(hundreds of degrees centigrade). The tristructuralisotropic(TRISO) as the fuel is independent in FHR core and its failure is limited for the core. The core damage in Level 1 PSA is of lower frequency. Levels 1 and 2 PSA are combined in the FHR PSA analysis. The initiating events analysis is the beginning, and the source term analysis and the release types are the target. Finally, Level3 PSA is done. 展开更多
关键词 高温气冷堆 概率安全评价 压水反应堆 框架分析 安全评估 氟盐 快中子反应堆 物理设计
下载PDF
上一页 1 下一页 到第
使用帮助 返回顶部