Plasma wall interaction in long-pulse helium discharge in LHD - Microscopic modification of the wall surface and its impact on particle balance and impurity generation

被引：33

作者：

Tokitani, M. ^{[1
]}

Kasahara, H. ^{[1
]}

Masuzaki, S. ^{[1
]}

Motojima, G. ^{[1
]}

Shoji, M. ^{[1
]}

Ueda, Y. ^{[2
]}

Yoshida, N. ^{[3
]}

Yoshimura, Y. ^{[1
]}

Nagasaki, K. ^{[4
]}

Ashikawa, N. ^{[1
]}

Mutoh, T. ^{[1
]}

Yamada, H. ^{[1
]}

Nagata, S. ^{[5
]}

机构：

[1] Natl Inst Fus Sci, Toki, Gifu 5095292, Japan

[2] Osaka Univ, Grad Sch Engn, Suita, Osaka 5650871, Japan

[3] Kyushu Univ, Appl Mech Res Inst, Kasuga, Fukuoka 8168580, Japan

[4] Kyoto Univ, Inst Adv Energy, Uji, Kyoto 6110011, Japan

[5] Tohoku Univ, Inst Mat Res, Sendai, Miyagi 9808577, Japan

来源：

JOURNAL OF NUCLEAR MATERIALS | 2015年 / 463卷

关键词：

OPERATION; TRIAM-1M; ENERGY;

D O I：

10.1016/j.jnucmat.2014.12.062

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Ultra-long-pulse helium discharge with ion and electron cyclotron heating (ICH + ECH) in the Large Helical Device (LHD) was achieved in a 48 min plasma (n(e) similar to 1.2 x 10(19) m(-3), T-i,T-e similar to 2 keV) with an average heating power of 1.2 MW. The temperature of the first-wall surface during discharges remained at nearly room temperature. However, even in ultra-long-pulse helium discharge, the discharge conditions cannot be said to be in a steady-state, because of two major issues interrupting the steady-state condition. One is the "dynamic change of the wall pumping rate" and the other is the "termination of the discharge with the exfoliation of the mixed-material deposition layers." Microscopic modifications, such as helium radiation damage and the formation of the mixed-material deposition layers composed of C (similar to 98%) and Fe (similar to 2%), on the plasma facing components (PFMs) were clarified to possibly influence the major issues. (C) 2014 Elsevier B.V. All rights reserved.

引用

页码：91 / 98

页数：8

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