Demonstration of ripple reduction by ferritic steel board insertion in JFT-2M

被引:39
作者
Kawashima, H [1 ]
Sato, M
Tsuzuki, K
Miura, Y
Isei, N
Kimura, H
Nakayama, T
Abe, M
Darrow, DS
机构
[1] Japan Atom Energy Res Inst, Naka Ku, Ibaraki, Osaka, Japan
[2] Hitachi Ltd, Ibaraki, Osaka, Japan
[3] Princeton Univ, Princeton Plasma Phys Lab, Princeton, NJ 08543 USA
关键词
D O I
10.1088/0029-5515/41/3/302
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
In the JFT-2M tokamak, the application of low activation ferritic steels to plasmas has been investigated (the so-called Advanced Material Tokamak Experiment (AMTEX) programme). In the first stage, toroidal field ripple reduction was examined by ferritic steel boards (FBs) inserted between the toroidal field coils and the vacuum vessel. It is demonstrated that FB insertion reduced toroidal field ripple and the losses of fast ions produced by tangential co-NBI. By optimizing the FB thickness, such that fundamental mode ripple is minimized to 0.07% at the shoulder of the inside wall, ripple trapped loss is reduced to an almost negligible level. It is determined that the reductions of the fundamental mode ripple and the ripple banana diffusion coefficients at the shoulder are most effective in reducing ripple ion losses. Ripple loss reduction by FBs is also confirmed with perpendicular beam injection. The insertion of FBs causes no undesirable effects on plasma production and control.
引用
收藏
页码:257 / 263
页数:7
相关论文
共 20 条
[1]   ALPHA-PARTICLE TRANSPORT PROCESSES IN TOKAMAKS [J].
GOLOBORODKO, VY ;
KOLESNICHENKO, YI ;
YAVORSKIJ, VA .
PHYSICA SCRIPTA, 1987, T16 :46-52
[2]  
ISEI N, IN PRESS FUSION TECH
[3]  
KIMURA H, 2000, 2000004 JAERI, P77
[4]  
KIMURA H, UNPUB FUSION ENG DES
[5]   CRITICAL ERROR FIELDS FOR LOCKED MODE-INSTABILITY IN TOKAMAKS [J].
LAHAYE, RJ ;
FITZPATRICK, R ;
HENDER, TC ;
MORRIS, AW ;
SCOVILLE, JT ;
TODD, TN .
PHYSICS OF FLUIDS B-PLASMA PHYSICS, 1992, 4 (07) :2098-2103
[6]   Evaluation of magnetic fields due to the ferromagnetic vacuum vessel and their influence on plasma discharge in tokamak devices [J].
Nakayama, T ;
Abe, M ;
Tadokoro, T ;
Otsuka, M .
JOURNAL OF NUCLEAR MATERIALS, 1999, 271 :491-495
[7]  
NAKAYAMA T, 1999, FUSION ENG, P227
[8]  
RICCI M, 1989, FUSION TECHNOL, P1565
[9]   Design and first experimental results of toroidal field ripple reduction using ferritic insertion in JFT-2M [J].
Sato, M ;
Kawashima, H ;
Miura, Y ;
Tsuzuki, K ;
Kimura, H ;
Uehara, K ;
Ogawa, T ;
Isei, N ;
Tani, T ;
Akiyama, T ;
Shibata, T ;
Yamamoto, M ;
Koike, T ;
Abe, M ;
Nakayama, T .
FUSION ENGINEERING AND DESIGN, 2000, 51-52 (51-52) :1071-1076
[10]   Analysis of error field due to ferritic steel in the advanced material testing program of JFT-2M [J].
Sato, M ;
Miura, Y ;
Takeji, S ;
Kimura, H ;
Shiba, K .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1253-1258