Overview and Status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX)

T. Gray, M.J. Williams, D. Ruzic
{"title":"Overview and Status of the Divertor Erosion and Vapor shielding eXperiment (DEVeX)","authors":"T. Gray, M.J. Williams, D. Ruzic","doi":"10.1109/FUSION.2007.4337925","DOIUrl":null,"url":null,"abstract":"The Divertor Erosion and Vapor shielding experiment (DEVeX) is being constructed at the University of Illinois at Urbana-Champaign to study how incident high enthalpy plasma flows interact with target materials representative of plasma facing components (PFCs). DEVeX consists of a conical, theta-pinch used to compress and expel plasmas relevant to fusion disruptions such as edge localized modes (ELMs). Modeling of the plasma compression, via a snow-plow model, shows expected plasma densities of 1021 m-3 with a temperature of approximately 1 keV for a duration of 100 mus. An overview of the design and performance of DEVeX will be presented along with current results.","PeriodicalId":124369,"journal":{"name":"2007 IEEE 22nd Symposium on Fusion Engineering","volume":"148 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2007-06-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"5","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"2007 IEEE 22nd Symposium on Fusion Engineering","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/FUSION.2007.4337925","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 5

Abstract

The Divertor Erosion and Vapor shielding experiment (DEVeX) is being constructed at the University of Illinois at Urbana-Champaign to study how incident high enthalpy plasma flows interact with target materials representative of plasma facing components (PFCs). DEVeX consists of a conical, theta-pinch used to compress and expel plasmas relevant to fusion disruptions such as edge localized modes (ELMs). Modeling of the plasma compression, via a snow-plow model, shows expected plasma densities of 1021 m-3 with a temperature of approximately 1 keV for a duration of 100 mus. An overview of the design and performance of DEVeX will be presented along with current results.
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
导流器冲蚀与蒸汽屏蔽实验(DEVeX)综述与现状
导流器侵蚀和蒸汽屏蔽实验(DEVeX)正在伊利诺伊大学厄巴纳-香槟分校进行,旨在研究入射高焓等离子体流如何与等离子体面向组件(pfc)代表的目标材料相互作用。DEVeX包括一个锥形的,用于压缩和驱逐与融合中断相关的等离子体,如边缘局域模式(elm)。通过雪犁模型对等离子体压缩进行建模,表明预期等离子体密度为1021 m-3,温度约为1 keV,持续时间为100 mus。DEVeX的设计和性能概述将与目前的结果一起提出。
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
自引率
0.00%
发文量
0
期刊最新文献
Low Pressure Operation of Radially Convergent Beam Fusion Using Differentially-Pumped Ion Sources A Fast visible camera Divertor-imaging diagnostic on DIII-D ITER Neutronics Analysis for the Design of Diagnostics and Port Plugs Using ATTILA Discrete Ordinates Software Divertor Heat Loads from Thermal and Alpha Particles in a Compact Stellarator Reactor Improvements of the DIII-D Cryosystem from Analysis of Failure Modes and Their Effects
×
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学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:604180095
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