High power (22 MW) ICRH at JET and developments for next step devices

T. Wade, J. Jacquinot, G. Bosia, A. Sibley, M. Schmid
{"title":"High power (22 MW) ICRH at JET and developments for next step devices","authors":"T. Wade, J. Jacquinot, G. Bosia, A. Sibley, M. Schmid","doi":"10.1109/FUSION.1991.218703","DOIUrl":null,"url":null,"abstract":"In excess of 22 MW of ion cyclotron resonance heating at the JET (Joint European Torus) plasma center has been achieved with increased plant availability by changes to the plant and its control and protection philosophy. Nested feedback systems, including RF control of the plasma position, enable power to be sustained throughout L mode to H mode fast plasma load variations. Modified plasma sawtooth behavior has been obtained by pi /2 phasing of the antenna currents. These control developments and the proposed fast wave current drive experiments with the new four-strap, JET ICRH antennas will be relevant to ITER (International Thermonuclear Experimental Reactor) and next step devices.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"116 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1991-09-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"6","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/FUSION.1991.218703","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 6

Abstract

In excess of 22 MW of ion cyclotron resonance heating at the JET (Joint European Torus) plasma center has been achieved with increased plant availability by changes to the plant and its control and protection philosophy. Nested feedback systems, including RF control of the plasma position, enable power to be sustained throughout L mode to H mode fast plasma load variations. Modified plasma sawtooth behavior has been obtained by pi /2 phasing of the antenna currents. These control developments and the proposed fast wave current drive experiments with the new four-strap, JET ICRH antennas will be relevant to ITER (International Thermonuclear Experimental Reactor) and next step devices.<>
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
JET的高功率(22兆瓦)ICRH和下一步设备的开发
在JET(欧洲联合环面)等离子体中心已经实现了超过22兆瓦的离子回旋共振加热,通过改变工厂及其控制和保护理念,增加了工厂的可用性。嵌套反馈系统,包括等离子体位置的射频控制,使功率在L模式到H模式的快速等离子体负载变化中保持持续。通过对天线电流进行π /2相位调整,得到了改进的等离子体锯齿状特性。这些控制技术的发展和使用新型四带、JET ICRH天线的快波电流驱动实验将与ITER(国际热核实验反应堆)和下一步设备相关。
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
Design of a coil to correct magnetic field errors on the DIII-D tokamak The charge exchange recombination diagnostic system on the DIII-D tokamak Software upgrade for the DIII-D neutral beam control systems Timing system for neutral beam injection on the DIII-D tokamak DIII-D radiation shielding procedures and experiences
×
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: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