Operational performance of JT-60U W-shaped divertor

被引:14
|
作者
Hosogane, N [1 ]
Tamai, H
Higashijima, S
Kubo, H
Sakasai, A
Takenaga, H
Itami, K
Sakurai, S
Asakura, N
Konoshima, S
Sugie, T
Shimizu, K
Ishijima, T
Kumagai, A
Suzuki, S
Shimada, M
机构
[1] Japan Atom Energy Res Inst, Naka Fus Res Estab, Naka, Ibaraki 31101, Japan
[2] Univ Tsukuba, Tsukuba, Ibaraki 305, Japan
关键词
JT-60U; divertor asymmetry; divertor pumping; impurity reduction;
D O I
10.1016/S0022-3115(98)00820-4
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Performance of inner leg pumping of JT-60U W-shaped divertor is presented. Inner leg pumping works well as the dome separates inner and outer divertor channels for neutral particles in the private flux region. In ELMy II-mode with NBI heating power of 18 MW, the operational regime where inner leg pumping is effective extends to the divertor radiation range of about 60% of SOL power. The fraction of inner particle flux pumped is estimated to be about 3%. It is qualitatively shown that a combination of main gas puff and inner leg pumping reduces carbon impurities in the main plasma, suggesting the existence of SOL flow effect on impurity reduction. (C) 1999 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:296 / 301
页数:6
相关论文
共 50 条
  • [11] Particle control and behaviour of neutrals in the pumped W-shaped divertor of JT-60U
    Tamai, H
    Asakura, N
    Hosogane, N
    Takenaga, H
    Higashijima, S
    Itami, K
    Konoshima, S
    Kubo, H
    Sakasai, A
    Sakurai, S
    Shimizu, K
    JOURNAL OF NUCLEAR MATERIALS, 1999, 266 : 1219 - 1223
  • [12] Particle control and behaviour of neutrals in the pumped W-shaped divertor of JT-60U
    Tamai, H.
    Asakura, N.
    Hosogane, N.
    Takenaga, H.
    Higashijima, S.
    Itami, K.
    Konoshima, S.
    Kubo, H.
    Sakasai, A.
    Sakurai, S.
    Shimizu, K.
    Journal of Nuclear Materials, 1999, 266 : 1219 - 1223
  • [13] Installation of the W-shaped diverter in JT-60U
    Kodama, K
    Sasajima, T
    Masaki, K
    Hosogane, N
    Sakurai, S
    Morimoto, M
    Miyo, Y
    Hiratsuka, H
    Akino, N
    Takahashi, S
    Kishiya, K
    Neyatani, Y
    Saidoh, M
    17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 365 - 368
  • [14] Radiative plasma by impurity seeding in W-shaped pumped divertor experiment of JT-60U
    Itami, K.
    Hosogane, N.
    Konoshima, S.
    Sakurai, S.
    Asakura, N.
    Higashijima, S.
    Sakasai, A.
    Tamai, H.
    Shimada, M.
    Journal of Nuclear Materials, 1999, 266 : 1097 - 1102
  • [15] Plasma characteristics near the X-point in W-shaped divertor of JT-60U
    Sakurai, S
    Asakura, N
    Hosogane, N
    Itami, K
    Shimada, M
    Naito, O
    JOURNAL OF NUCLEAR MATERIALS, 1999, 266 : 1191 - 1196
  • [16] Particle control and SOL plasma flow in the W-shaped divertor of JT-60U tokamak
    Asakura, N
    Takenaga, H
    Sakurai, S
    Tamai, H
    Sakasai, A
    Shimizu, K
    Porter, GD
    PLASMA PHYSICS AND CONTROLLED FUSION, 2002, 44 (10) : 2101 - 2119
  • [17] Plasma characteristics near the X-point in W-shaped divertor of JT-60U
    Japan Atom. Ener. Research Institute, Naka Fusion Research Establishment, Naki-machi, Naka-gun, Ibaraki 311-01, Japan
    J Nucl Mater, (1191-1196):
  • [18] Radiative plasma by impurity seeding in W-shaped pumped divertor experiment of JT-60U
    Itami, K
    Hosogane, N
    Konoshima, S
    Sakurai, S
    Asakura, N
    Higashijima, S
    Sakasai, A
    Tamai, H
    Shimada, M
    JOURNAL OF NUCLEAR MATERIALS, 1999, 266 : 1097 - 1102
  • [19] Hydrogen isotope retention of JT-60U W-shaped divertor tiles exposed to DD discharges
    Shibahara, T.
    Tanabe, T.
    Hirohata, Y.
    Oya, Y.
    Oyaidzu, M.
    Yoshikawa, A.
    Onishi, Y.
    Arai, T.
    Masaki, K.
    Okuno, K.
    Miya, N.
    JOURNAL OF NUCLEAR MATERIALS, 2006, 357 (1-3) : 115 - 125
  • [20] Deuterium depth profiling in JT-60U W-shaped divertor tiles by nuclear reaction analysis
    Hayashi, T
    Ochiai, K
    Masaki, K
    Gotoh, Y
    Kutsukake, C
    Arai, T
    Nishitani, T
    Miya, N
    JOURNAL OF NUCLEAR MATERIALS, 2006, 349 (1-2) : 6 - 16