Edge diagnostics and transport in the TEXT tokamak

Ch P. Ritz; R. V. Bravenec; R. D. Bengtson; K. W. Gentle; C. C. Klepper; P. E. Phillips; E. J. Powers; T. L. Rhodes; B. Richards; William L. Rowan; A. J. Wootton

doi:10.1016/0022-3115(87)90335-7

Edge diagnostics and transport in the TEXT tokamak

Ch P. Ritz, R. V. Bravenec, R. D. Bengtson, K. W. Gentle, C. C. Klepper, P. E. Phillips, E. J. Powers, T. L. Rhodes, B. Richards, William L. Rowan, A. J. Wootton

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

14 Scopus citations

Abstract

Particle and energy flux analysis in the edge region based on measured profiles are presented for one discharge condition of the Texas Experimental Tokamak (TEXT). The results are compared with measurements of fluctuation induced transport and with the predictions of two theoretical models for turbulence. Electrostatic turbulence can account for most of the total particle flux and the convected heat flux at the limiter. The scaling of the radial transport in the scrape-off layer can be accounted for by the fluctuations. In low density discharges the conducted heat flux cannot be attributed only to the measured fluctuations. For high density discharges, electrostatic fluctuations may be able to account for the conducted heat flux. The radial scaling of the particle flux from the resistivity gradient model agrees within a factor of three in the edge with the observed profile.

Original language	English
Pages (from-to)	241-244
Number of pages	4
Journal	Journal of Nuclear Materials
Volume	145-147
Issue number	C
DOIs	https://doi.org/10.1016/0022-3115(87)90335-7
State	Published - Feb 2 1987
Externally published	Yes

Funding

We would like to thank P.H. Diamond, T.S. Hahm and P. Terry for helpful discussions. We would also like to thank the rest of the TEXT staff for their assistance in these experiments. This work is supported by the US Department of Energy Contract DE-AC0578ET-53043. The signal processing techniques were developed under the auspiceso f the Department of Defense Joint Services Electronics Program Contract F49620-82-C-0033..

Funders	Funder number
US Department of Energy	DE-AC0578ET-53043

Keywords

fluctuating fields
plasma-edge diagnostics
plasma-edge heat flux

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/0022-3115(87)90335-7

Cite this

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title = "Edge diagnostics and transport in the TEXT tokamak",

abstract = "Particle and energy flux analysis in the edge region based on measured profiles are presented for one discharge condition of the Texas Experimental Tokamak (TEXT). The results are compared with measurements of fluctuation induced transport and with the predictions of two theoretical models for turbulence. Electrostatic turbulence can account for most of the total particle flux and the convected heat flux at the limiter. The scaling of the radial transport in the scrape-off layer can be accounted for by the fluctuations. In low density discharges the conducted heat flux cannot be attributed only to the measured fluctuations. For high density discharges, electrostatic fluctuations may be able to account for the conducted heat flux. The radial scaling of the particle flux from the resistivity gradient model agrees within a factor of three in the edge with the observed profile.",

keywords = "fluctuating fields, plasma-edge diagnostics, plasma-edge heat flux",

author = "Ritz, {Ch P.} and Bravenec, {R. V.} and Bengtson, {R. D.} and Gentle, {K. W.} and Klepper, {C. C.} and Phillips, {P. E.} and Powers, {E. J.} and Rhodes, {T. L.} and B. Richards and Rowan, {William L.} and Wootton, {A. J.}",

year = "1987",

month = feb,

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doi = "10.1016/0022-3115(87)90335-7",

language = "English",

volume = "145-147",

pages = "241--244",

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T1 - Edge diagnostics and transport in the TEXT tokamak

AU - Ritz, Ch P.

AU - Bravenec, R. V.

AU - Bengtson, R. D.

AU - Gentle, K. W.

AU - Klepper, C. C.

AU - Phillips, P. E.

AU - Powers, E. J.

AU - Rhodes, T. L.

AU - Richards, B.

AU - Rowan, William L.

AU - Wootton, A. J.

PY - 1987/2/2

Y1 - 1987/2/2

N2 - Particle and energy flux analysis in the edge region based on measured profiles are presented for one discharge condition of the Texas Experimental Tokamak (TEXT). The results are compared with measurements of fluctuation induced transport and with the predictions of two theoretical models for turbulence. Electrostatic turbulence can account for most of the total particle flux and the convected heat flux at the limiter. The scaling of the radial transport in the scrape-off layer can be accounted for by the fluctuations. In low density discharges the conducted heat flux cannot be attributed only to the measured fluctuations. For high density discharges, electrostatic fluctuations may be able to account for the conducted heat flux. The radial scaling of the particle flux from the resistivity gradient model agrees within a factor of three in the edge with the observed profile.

AB - Particle and energy flux analysis in the edge region based on measured profiles are presented for one discharge condition of the Texas Experimental Tokamak (TEXT). The results are compared with measurements of fluctuation induced transport and with the predictions of two theoretical models for turbulence. Electrostatic turbulence can account for most of the total particle flux and the convected heat flux at the limiter. The scaling of the radial transport in the scrape-off layer can be accounted for by the fluctuations. In low density discharges the conducted heat flux cannot be attributed only to the measured fluctuations. For high density discharges, electrostatic fluctuations may be able to account for the conducted heat flux. The radial scaling of the particle flux from the resistivity gradient model agrees within a factor of three in the edge with the observed profile.

KW - fluctuating fields

KW - plasma-edge diagnostics

KW - plasma-edge heat flux

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U2 - 10.1016/0022-3115(87)90335-7

DO - 10.1016/0022-3115(87)90335-7

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SN - 0022-3115

VL - 145-147

SP - 241

EP - 244

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - C

ER -

Edge diagnostics and transport in the TEXT tokamak

Abstract

Funding

Keywords

UN SDGs

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