プラズマ・核融合学会誌
Print ISSN : 0918-7928
研究論文
JFT-2M における低放射化フェライト鋼のプラズマ適合性試験˜真空容器内への部分的設置˜
都筑 和泰伊世井 宣明川島 寿人佐藤 正泰木村 晴行小川 宏明三浦 幸俊小川 俊英柴田 孝俊秋山 隆岡野 文範鈴木 貞明山本 正弘宮地 謙吾JFT-2M グループ??
著者情報
ジャーナル フリー

2002 年 78 巻 5 号 p. 455-461

詳細
抄録

The compatibility of reduced activation ferritic steel (F82H), which is a leading candidate material for the demo reactor (e.g. SSTR), with plasma has been investigated in the JFT-2M tokamak with 3 steps in an AMTEX (Advanced Material Tokamak EXperiment). In the first step, the reduction of fast ion losses was well demonstrated with the ferritic steel outside the vacuum vessel. In the second step, the ferritic steel was installed inside the vacuum vessel in order to perform a preliminary investigation of the effect of the ferro-magnetism on plasma stability and control, and impurity release. For this purpose, ferritic steels of 7 mm thickness were installed to form 2 sets of toroidally uniform belts, which cover 20% of the vacuum vessel. No deteriorative effects were observed regarding mode locking, plasma control, and impurity desorption. The initial boron coating was applied in order to modify the surface of the ferritic steel. The impurity is remarkably reduced and high normalized-beta plasma was obtained. Thus encouraging results were obtained for the third step, where whole vacuum vessel wall will be covered with ferritic steel.

著者関連情報
© 2002 by The Japan Society of Plasma Science and Nuclear Fusion Research (Japanese)
前の記事 次の記事
feedback
Top