2017年
Current Status of Large Helical Device and Its Prospect for Deuterium Experiment
FUSION SCIENCE AND TECHNOLOGY
- 巻
- 72
- 号
- 3
- 開始ページ
- 199
- 終了ページ
- 210
- 記述言語
- 英語
- 掲載種別
- DOI
- 10.1080/15361055.2017.1335145
- 出版者・発行元
- TAYLOR & FRANCIS INC
Achievement of reactor relevant plasma condition in Helical type magnetic devices and exploration in its related plasma physics and fusion engineering are the aim of the Large Helical Device (LHD) project. In the recent experiments on LHD, we have achieved ion-temperature of 8.1 keV at 1 x 10(19) m(-3) by the optimization of wall conditioning using long pulse discharge by Ion Cyclotron Heating (ICH). The electron temperature of 10 keV at 1.6 x 10(19) m(-3) was also achieved by the optimization of Electron Cyclotron Heating (ECH). For further improvement in plasma performance, the upgrade of the Large Helical Device (LHD), including the deuterium experiment, is planned. In this paper, the recent achievements on LHD and the upgrade of LHD are described.
- リンク情報
-
- DOI
- https://doi.org/10.1080/15361055.2017.1335145
- Web of Science
- https://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcAuth=JSTA_CEL&SrcApp=J_Gate_JST&DestLinkType=FullRecord&KeyUT=WOS:000416678000002&DestApp=WOS_CPL
- URL
- https://www.scopus.com/inward/record.uri?partnerID=HzOxMe3b&scp=85029958347&origin=inward
- ID情報
-
- DOI : 10.1080/15361055.2017.1335145
- ISSN : 1536-1055
- eISSN : 1943-7641
- SCOPUS ID : 85029958347
- Web of Science ID : WOS:000416678000002