中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
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; Liu, Songlin2; Xu, Bai-Chuan1,2; Li, Xiao-Chun2
刊名NUCLEAR MATERIALS AND ENERGY
出版日期2024-09-01
卷号40
关键词WCCB blanket Tritium transport Tritium inventory Tritium losses
DOI10.1016/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

浏览0
下载0
收藏0
其他版本

除非特别说明,本系统中所有内容都受版权保护,并保留所有权利。