Preliminary tritium transport analysis for the water cooled ceramic breeder blanket system based on a system level code
文献类型:期刊论文
作者 | Zhao, Xueli3; Yang, Wanhuan3; Chen, Lei2![]() ![]() ![]() |
刊名 | NUCLEAR MATERIALS AND ENERGY
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出版日期 | 2024-09-01 |
卷号 | 40 |
关键词 | WCCB blanket Tritium transport Tritium inventory Tritium losses |
DOI | 10.1016/j.nme.2024.101703 |
通讯作者 | Li, Xiao-Chun(xcli@ipp.ac.cn) |
英文摘要 | This paper presents a dynamic analysis tool for evaluating the tritium inventory, tritium extraction and tritium losses for the Water Cooled Ceramic Breeder (WCCB) blanket system of Chinese Fusion Engineering Test Reactor (CFETR). We have developed a program for the tritium transport analysis at the system level, which aims to estimate the tritium related quantities for the WCCB blanket system. The tritium inventory in the material defects is likewise taken into account. The sensitivity analysis is conducted on key parameters is carried out. The key output quantities of the WCCB blanket system include the tritium inventory in structural material, purge gas and coolant loops, tritium extracted by the TES and CPS, and tritium losses. |
WOS关键词 | UNIT LEVEL ; DESIGN ; MODEL ; PERMEATION ; BEHAVIOR ; HCLL |
资助项目 | National Magnetic Confinement Fusion Energy Special Project[2019YFE03110000] ; National Magnetic Confinement Fusion Energy Special Project[2019YFE03110002] ; National natural science foundation of China[11775256] ; National natural science foundation of China[11975260] |
WOS研究方向 | Nuclear Science & Technology |
语种 | 英语 |
WOS记录号 | WOS:001268582900001 |
出版者 | ELSEVIER |
资助机构 | National Magnetic Confinement Fusion Energy Special Project ; National natural science foundation of China |
源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/137077] ![]() |
专题 | 中国科学院合肥物质科学研究院 |
通讯作者 | Li, Xiao-Chun |
作者单位 | 1.Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China 2.Chinese Acad Sci, Hefei Inst Phys Sci, Inst Plasma Phys, Hefei 230031, Peoples R China 3.China Inst Atom Energy, Div Reactor Engn Technol Res, Beijing 102413, Peoples R China |
推荐引用方式 GB/T 7714 | Zhao, Xueli,Yang, Wanhuan,Chen, Lei,et al. Preliminary tritium transport analysis for the water cooled ceramic breeder blanket system based on a system level code[J]. NUCLEAR MATERIALS AND ENERGY,2024,40. |
APA | Zhao, Xueli,Yang, Wanhuan,Chen, Lei,Liu, Songlin,Xu, Bai-Chuan,&Li, Xiao-Chun.(2024).Preliminary tritium transport analysis for the water cooled ceramic breeder blanket system based on a system level code.NUCLEAR MATERIALS AND ENERGY,40. |
MLA | Zhao, Xueli,et al."Preliminary tritium transport analysis for the water cooled ceramic breeder blanket system based on a system level code".NUCLEAR MATERIALS AND ENERGY 40(2024). |
入库方式: OAI收割
来源:合肥物质科学研究院
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