Plasma-surface interactions in the Alcator C-Mod tokamak

B. Lipschultz; J. Goetz; B. LaBombard; G. McCracken; J. Terry; D. Jablonski; C. Kurz; A. Niemczewski; J. Snipes

doi:10.1016/0022-3115(94)00452-8

Plasma-surface interactions in the Alcator C-Mod tokamak

B. Lipschultz
, J. Goetz
, B. LaBombard
, G. McCracken
, J. Terry
, D. Jablonski
, C. Kurz
, A. Niemczewski
, J. Snipes

Research output: Contribution to journal › Article › peer-review

12 Scopus citations

Abstract

Alcator C-Mod is a high-field tokamak with which experiments were initiated in April 1993. The divertor and the first-wall have plasma-facing surfaces of molybdenum. The divertor has a configuration which is closed in comparison to other, currently operating tokamaks. The combination of divertor geometry and high field (density) make Alcator C-Mod an ideal experiment to investigate dissipative (radiative/CX) divertor scenarios. Single-null divertor operation has become the standard mode of operation. Relatively clean plasmas (Z_eff ≤ 1.3) are obtained with short periods of baking and electron cyclotron discharge cleaning only. Impurity source rates and screening have been investigated with an extensive set of wavelength-filtered diode arrays and spectrographs. Carbon and oxygen and molybdenum dominate the impurity levels. The molybdenum source from the divertor proper is negligible.

Original language	English (US)
Pages (from-to)	967-970
Number of pages	4
Journal	Journal of Nuclear Materials
Volume	220-222
DOIs	https://doi.org/10.1016/0022-3115(94)00452-8
State	Published - 1995
Externally published	Yes

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
General Materials Science
Nuclear Energy and Engineering

Access to Document

10.1016/0022-3115(94)00452-8

Cite this

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title = "Plasma-surface interactions in the Alcator C-Mod tokamak",

abstract = "Alcator C-Mod is a high-field tokamak with which experiments were initiated in April 1993. The divertor and the first-wall have plasma-facing surfaces of molybdenum. The divertor has a configuration which is closed in comparison to other, currently operating tokamaks. The combination of divertor geometry and high field (density) make Alcator C-Mod an ideal experiment to investigate dissipative (radiative/CX) divertor scenarios. Single-null divertor operation has become the standard mode of operation. Relatively clean plasmas (Zeff ≤ 1.3) are obtained with short periods of baking and electron cyclotron discharge cleaning only. Impurity source rates and screening have been investigated with an extensive set of wavelength-filtered diode arrays and spectrographs. Carbon and oxygen and molybdenum dominate the impurity levels. The molybdenum source from the divertor proper is negligible.",

author = "B. Lipschultz and J. Goetz and B. LaBombard and G. McCracken and J. Terry and D. Jablonski and C. Kurz and A. Niemczewski and J. Snipes",

year = "1995",

doi = "10.1016/0022-3115(94)00452-8",

language = "English (US)",

volume = "220-222",

pages = "967--970",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

}

TY - JOUR

T1 - Plasma-surface interactions in the Alcator C-Mod tokamak

AU - Lipschultz, B.

AU - Goetz, J.

AU - LaBombard, B.

AU - McCracken, G.

AU - Terry, J.

AU - Jablonski, D.

AU - Kurz, C.

AU - Niemczewski, A.

AU - Snipes, J.

PY - 1995

Y1 - 1995

N2 - Alcator C-Mod is a high-field tokamak with which experiments were initiated in April 1993. The divertor and the first-wall have plasma-facing surfaces of molybdenum. The divertor has a configuration which is closed in comparison to other, currently operating tokamaks. The combination of divertor geometry and high field (density) make Alcator C-Mod an ideal experiment to investigate dissipative (radiative/CX) divertor scenarios. Single-null divertor operation has become the standard mode of operation. Relatively clean plasmas (Zeff ≤ 1.3) are obtained with short periods of baking and electron cyclotron discharge cleaning only. Impurity source rates and screening have been investigated with an extensive set of wavelength-filtered diode arrays and spectrographs. Carbon and oxygen and molybdenum dominate the impurity levels. The molybdenum source from the divertor proper is negligible.

AB - Alcator C-Mod is a high-field tokamak with which experiments were initiated in April 1993. The divertor and the first-wall have plasma-facing surfaces of molybdenum. The divertor has a configuration which is closed in comparison to other, currently operating tokamaks. The combination of divertor geometry and high field (density) make Alcator C-Mod an ideal experiment to investigate dissipative (radiative/CX) divertor scenarios. Single-null divertor operation has become the standard mode of operation. Relatively clean plasmas (Zeff ≤ 1.3) are obtained with short periods of baking and electron cyclotron discharge cleaning only. Impurity source rates and screening have been investigated with an extensive set of wavelength-filtered diode arrays and spectrographs. Carbon and oxygen and molybdenum dominate the impurity levels. The molybdenum source from the divertor proper is negligible.

UR - https://www.scopus.com/pages/publications/84862544941

UR - https://www.scopus.com/pages/publications/84862544941#tab=citedBy

U2 - 10.1016/0022-3115(94)00452-8

DO - 10.1016/0022-3115(94)00452-8

M3 - Article

AN - SCOPUS:84862544941

SN - 0022-3115

VL - 220-222

SP - 967

EP - 970

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Plasma-surface interactions in the Alcator C-Mod tokamak

Abstract

All Science Journal Classification (ASJC) codes

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