Framework analysis of fluoride salt-cooled high temperature reactor probabilistic safety assessment
Zuo, JX; Jing, JP; Bi, JS; Song, W; Chen, K; Song, W (reprint author), Minist Environm Protect, Nucl & Radiat Safety Ctr, Beijing 100082, Peoples R China.
2015
发表期刊NUCLEAR SCIENCE AND TECHNIQUES
ISSN1001-8042
卷号26期号:5页码:
文章类型期刊文献
摘要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 gas-cooled 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 tristructural-isotropic (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, Level 3 PSA is done.
收录类别SCI
语种英语
WOS记录号WOS:000365459200020
引用统计
被引频次:4[WOS]   [WOS记录]     [WOS相关记录]
文献类型期刊论文
条目标识符http://ir.sinap.ac.cn/handle/331007/24932
专题中科院上海应用物理研究所2011-2018年
通讯作者Song, W (reprint author), Minist Environm Protect, Nucl & Radiat Safety Ctr, Beijing 100082, Peoples R China.
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GB/T 7714
Zuo, JX,Jing, JP,Bi, JS,et al. Framework analysis of fluoride salt-cooled high temperature reactor probabilistic safety assessment[J]. NUCLEAR SCIENCE AND TECHNIQUES,2015,26(5):—.
APA Zuo, JX,Jing, JP,Bi, JS,Song, W,Chen, K,&Song, W .(2015).Framework analysis of fluoride salt-cooled high temperature reactor probabilistic safety assessment.NUCLEAR SCIENCE AND TECHNIQUES,26(5),—.
MLA Zuo, JX,et al."Framework analysis of fluoride salt-cooled high temperature reactor probabilistic safety assessment".NUCLEAR SCIENCE AND TECHNIQUES 26.5(2015):—.
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