A scaling relation for the ITER scrape-off layer thermal diffusivity

S. A. Cohen; Ömer Artun

doi:10.1016/S0022-3115(06)80162-5

A scaling relation for the ITER scrape-off layer thermal diffusivity

S. A. Cohen, Ömer Artun

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

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Abstract

We have generated an empirically based scaling relation for the thermal diffusivity, _sχ_⊥, in the scrape-off layers (SOL) of tokamaks using a database of global energy confinement time versus core plasma parameters from 110 ohmically heated tokamak discharges whose core plasma parameters, viz., T_e, n_e, B, curvature, radial scale length, and Z_eff, are similar to the values expected in the SOL of tokamaks like ITER. These data were interpreted with an all-possible-regressions model/multiple-regressions analysis to obtain the best fit for τ_E versus n_e, T_e, R, a, Z_eff and V. A cylindrical-shell thermal transport model was used to extract _sχ_⊥ from τ_E. Reasons for ignoring the effects on _sχ_⊥ of sheath phenomena and parallel transport on open field lines are discussed.

Original language	English (US)
Pages (from-to)	888-893
Number of pages	6
Journal	Journal of Nuclear Materials
Volume	196-198
Issue number	C
DOIs	https://doi.org/10.1016/S0022-3115(06)80162-5
State	Published - Dec 1 1992

All Science Journal Classification (ASJC) codes

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

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10.1016/S0022-3115(06)80162-5

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title = "A scaling relation for the ITER scrape-off layer thermal diffusivity",

abstract = "We have generated an empirically based scaling relation for the thermal diffusivity, sχ⊥, in the scrape-off layers (SOL) of tokamaks using a database of global energy confinement time versus core plasma parameters from 110 ohmically heated tokamak discharges whose core plasma parameters, viz., Te, ne, B, curvature, radial scale length, and Zeff, are similar to the values expected in the SOL of tokamaks like ITER. These data were interpreted with an all-possible-regressions model/multiple-regressions analysis to obtain the best fit for τE versus ne, Te, R, a, Zeff and V. A cylindrical-shell thermal transport model was used to extract sχ⊥ from τE. Reasons for ignoring the effects on sχ⊥ of sheath phenomena and parallel transport on open field lines are discussed.",

author = "Cohen, {S. A.} and {\"O}mer Artun",

year = "1992",

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doi = "10.1016/S0022-3115(06)80162-5",

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T1 - A scaling relation for the ITER scrape-off layer thermal diffusivity

AU - Cohen, S. A.

AU - Artun, Ömer

PY - 1992/12/1

Y1 - 1992/12/1

N2 - We have generated an empirically based scaling relation for the thermal diffusivity, sχ⊥, in the scrape-off layers (SOL) of tokamaks using a database of global energy confinement time versus core plasma parameters from 110 ohmically heated tokamak discharges whose core plasma parameters, viz., Te, ne, B, curvature, radial scale length, and Zeff, are similar to the values expected in the SOL of tokamaks like ITER. These data were interpreted with an all-possible-regressions model/multiple-regressions analysis to obtain the best fit for τE versus ne, Te, R, a, Zeff and V. A cylindrical-shell thermal transport model was used to extract sχ⊥ from τE. Reasons for ignoring the effects on sχ⊥ of sheath phenomena and parallel transport on open field lines are discussed.

AB - We have generated an empirically based scaling relation for the thermal diffusivity, sχ⊥, in the scrape-off layers (SOL) of tokamaks using a database of global energy confinement time versus core plasma parameters from 110 ohmically heated tokamak discharges whose core plasma parameters, viz., Te, ne, B, curvature, radial scale length, and Zeff, are similar to the values expected in the SOL of tokamaks like ITER. These data were interpreted with an all-possible-regressions model/multiple-regressions analysis to obtain the best fit for τE versus ne, Te, R, a, Zeff and V. A cylindrical-shell thermal transport model was used to extract sχ⊥ from τE. Reasons for ignoring the effects on sχ⊥ of sheath phenomena and parallel transport on open field lines are discussed.

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - C

ER -

A scaling relation for the ITER scrape-off layer thermal diffusivity

Abstract

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