中国科学院上海应用物理研究所机构知识库
Advanced  
CAS OpenIR  > 中科院上海应用物理研究所2011-2017年  > 期刊论文
题名:
Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward
作者: Forsberg, CW; Lam, S; Carpenter, DM; Whyte, DG; Scarlat, R; Contescu, C; Wei, L; Stempien, J; Blandford, E
刊名: NUCLEAR TECHNOLOGY
出版日期: 2017
卷号: 197, 期号:2, 页码:119-139
关键词: Tritium ; salt-cooled reactor ; fission ; fusion
DOI: 10.13182/NT16-101
文章类型: 期刊论文
英文摘要: Three advanced nuclear power systems use liquid salt coolants that generate tritium and thus face the common challenges of containing and capturing tritium to prevent its release to the environment. The fluoride salt-cooled high-temperature reactor (FHR) uses clean fluoride salt coolants and the same graphite-matrix coated-particle fuel as high-temperature gas-cooled reactors. Molten salt reactors (MSRs) dissolve the fuel in a fluoride or chloride salt with release of fission product tritium into the salt. In most FHR and MSR systems, the baseline salts contain lithium where isotopically separated Li-7 is proposed to minimize tritium production from neutron interactions with the salt. The Chinese Academy of Sciences plans to start operation of a 2-MW(thermal) molten salt test reactor by 2020. For high-magnetic-field fusion machines, the use of lithium enriched in Li-6 is proposed to maximize tritium generation-the fuel for a fusion machine. Advances in superconductors that enable higher power densities may require the use of molten lithium salts for fusion blankets and as coolants. Recent technical advances in these three reactor classes have resulted in increased government and private interest and the beginning of a coordinated effort to address the tritium control challenges in 700 degrees C liquid salt systems. We describe characteristics of salt-cooled fission and fusion machines, the basis for growing interest in these technologies, tritium generation in molten salts, the environment for tritium capture, models for high-temperature tritium transport in salt systems, alternative strategies for tritium control, and ongoing experimental work. Several methods to control tritium appear viable. Limited experimental data are the primary constraint for designing efficient cost-effective methods of tritium control.
收录类别: SCI
语种: 英语
WOS记录号: WOS:000397232700001
ISSN号: 0029-5450
Citation statistics:
内容类型: 期刊论文
URI标识: http://ir.sinap.ac.cn/handle/331007/27489
Appears in Collections:中科院上海应用物理研究所2011-2017年_期刊论文

Files in This Item:
File Name/ File Size Content Type Version Access License
Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors_ Status, Challenges, and Path Forward.pdf(3077KB)期刊论文作者接受稿开放获取View 联系获取全文

Recommended Citation:
Forsberg, CW,Lam, S,Carpenter, DM,et al. Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors: Status, Challenges, and Path Forward[J]. NUCLEAR TECHNOLOGY,2017-01-01,197(2):119-139.
Service
Recommend this item
Sava as my favorate item
Show this item's statistics
Export Endnote File
Google Scholar
Similar articles in Google Scholar
[Forsberg, CW]'s Articles
[Lam, S]'s Articles
[Carpenter, DM]'s Articles
CSDL cross search
Similar articles in CSDL Cross Search
[Forsberg, CW]‘s Articles
[Lam, S]‘s Articles
[Carpenter, DM]‘s Articles
Related Copyright Policies
Null
Social Bookmarking
Add to CiteULike Add to Connotea Add to Del.icio.us Add to Digg Add to Reddit
文件名: Tritium Control and Capture in Salt-Cooled Fission and Fusion Reactors_ Status, Challenges, and Path Forward.pdf
格式: Adobe PDF
所有评论 (0)
暂无评论
 
评注功能仅针对注册用户开放,请您登录
您对该条目有什么异议,请填写以下表单,管理员会尽快联系您。
内 容:
Email:  *
单位:
验证码:   刷新
您在IR的使用过程中有什么好的想法或者建议可以反馈给我们。
标 题:
 *
内 容:
Email:  *
验证码:   刷新

Items in IR are protected by copyright, with all rights reserved, unless otherwise indicated.

 

 

Valid XHTML 1.0!
Powered by CSpace