Framework analysis of fluoride salt-cooled high temperature reactor probabilistic safety assessment
文献类型：期刊论文
| 作者 | Zuo, JX; Jing, JP; Bi, JS; Song, W; Chen, K |
| 刊名 | NUCLEAR SCIENCE AND TECHNIQUES
 |
| 出版日期 | 2015 |
| 卷号 | 26期号:5页码:— |
| ISSN号 | 1001-8042 |
| 通讯作者 | Song, W (reprint author), Minist Environm Protect, Nucl & Radiat Safety Ctr, Beijing 100082, Peoples R China. |
| 英文摘要 | 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 |
| 公开日期 | 2016-03-08 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/24932]  |
| 专题 | 上海应用物理研究所_中科院上海应用物理研究所2011-2017年 |
| 推荐引用方式 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.(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):—. |
入库方式： OAI收割
来源：上海应用物理研究所
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