Overview of impurity control and wall conditioning in NSTX

被引：19

作者：

Kugel, HW

Maingi, R

Wampler, W

Barry, RE

Bell, M

Blanchard, W

Gates, D

Johnson, D

Kaita, R

Kaye, S

Maqueda, R

Menard, J

Menon, MM

Mueller, D

Ono, M

Paul, S

Peng, YKM

Raman, R

Roquemore, A

Skinner, CH

Sabbagh, S

Stratton, B

Stutman, D

Wilson, JR

Zweben, S

机构：

[1] Princeton Plasma Phys Lab, Princeton, NJ 08543 USA

[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA

[3] Los Alamos Natl Lab, Los Alamos, NM 87545 USA

[4] Univ Washington, Seattle, WA 98195 USA

[5] Columbia Univ, New York, NY 10027 USA

[6] Johns Hopkins Univ, Baltimore, MD 21218 USA

[7] Sandia Natl Labs, Albuquerque, NM 87123 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2001年 / 290卷

关键词：

wall conditioning; impurity control; glow discharge cleaning;

D O I：

10.1016/S0022-3115(00)00496-7

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The national spherical torus experiment (NSTX) started plasma operations in February 1999. In the first extended period of experiments, NSTX achieved high current, inner wall limited, double null, and single null plasma discharges, initial Coaxial Helicity Injection, and high harmonic fast wave results. As expected, discharge reproducibility and performance were strongly affected by wall conditions. In this paper, we describe the internal geometry, and initial plasma discharge, impurity control, wail conditioning, erosion, and deposition results. (C) 2001 Elsevier Science B.V. All rights reserved.

引用

页码：1185 / 1189

页数：5

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