On heat removal from the first-wall elements and warm toroidal field coils in the JUST-T tokamak

E. Azizov, G. G. Gladush, N. Rodionov, V. Rodionova
{"title":"On heat removal from the first-wall elements and warm toroidal field coils in the JUST-T tokamak","authors":"E. Azizov, G. G. Gladush, N. Rodionov, V. Rodionova","doi":"10.1080/10519990701451002","DOIUrl":null,"url":null,"abstract":"Heat removal from the structural elements of a compact tokamak with warm coils intended for the transmutation of minor actinides is an especially critical problem. This paper is concerned with the thermal processes on the first-wall elements and the toroidal field windings, ignoring the most stressed component of JUST-T, i.e. the blanket. The analysis has shown that the peak load on the first-wall elements in JUST-T does not exceed a similar load in the International Thermonuclear Experimental Reactor tokamak. The two-dimensional numerical code for calculation of the current distribution density, Ohmic heating and heat transfer due to heat conductivity and extraction of heat by the water flux has been developed.","PeriodicalId":54600,"journal":{"name":"Plasma Devices and Operations","volume":"48 48 1","pages":"241 - 252"},"PeriodicalIF":0.0000,"publicationDate":"2007-07-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Plasma Devices and Operations","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1080/10519990701451002","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 0

Abstract

Heat removal from the structural elements of a compact tokamak with warm coils intended for the transmutation of minor actinides is an especially critical problem. This paper is concerned with the thermal processes on the first-wall elements and the toroidal field windings, ignoring the most stressed component of JUST-T, i.e. the blanket. The analysis has shown that the peak load on the first-wall elements in JUST-T does not exceed a similar load in the International Thermonuclear Experimental Reactor tokamak. The two-dimensional numerical code for calculation of the current distribution density, Ohmic heating and heat transfer due to heat conductivity and extraction of heat by the water flux has been developed.
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
JUST-T托卡马克第一壁元件和暖环形场线圈的散热研究
用于小锕系元素嬗变的带有热线圈的紧凑型托卡马克的结构元件的散热是一个特别关键的问题。本文关注的是第一壁单元和环形场绕组的热过程,忽略了JUST-T中应力最大的部分,即包层。分析表明,JUST-T第一壁元件的峰值负荷不超过国际热核实验堆托卡马克的类似负荷。开发了计算电流分布密度、欧姆加热和导热传热以及水通量吸热的二维数值计算程序。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 去求助
来源期刊
Plasma Devices and Operations
Plasma Devices and Operations 物理-核科学技术
自引率
0.00%
发文量
0
期刊最新文献
Merger announcement Preliminary plasma focus studies at ODAK-3K device using track detectors Stray magnetic field produced by ITER tokamak complex Generation of degenerate modes in suddenly created cold weakly nonlinear magnetized plasma Investigations of mirrors for ITER diagnostics in modern fusion devices
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1