Models of SOL transport and their relation to scaling of the divertor heat flux width in DIII-D

Makowski, M. A.; Lasnier, C. J.; Leonard, A. W.; Osborne, T. H.; Umansky, M.; Elder, J. D.; Nichols, J. H.; Stangeby, P. C.; Baver, D. A.; Myra, J. R.

doi:10.1016/j.jnucmat.2014.09.065

Title: Models of SOL transport and their relation to scaling of the divertor heat flux width in DIII-D

Journal Article · Mon Oct 06 00:00:00 EDT 2014 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2014.09.065· OSTI ID:1345540

Makowski, M. A. ^[1]; Lasnier, C. J. ^[1]; Leonard, A. W. ^[2]; Osborne, T. H. ^[2]; Umansky, M. ^[1]; Elder, J. D. ^[3]; Nichols, J. H. ^[4]; Stangeby, P. C. ^[3]; Baver, D. A. ^[5]; Myra, J. R. ^[5]

Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
General Atomics, San Diego, CA (United States)
Univ. of Toronto, ON (Canada). Inst. for Aerospace Studies
Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
Lodestar Research Corp., Boulder, CO (United States)

Strong support for the critical pressure gradient model for the heat flux width has been obtained, in that the measured separatrix pressure gradient lies below and scales similarly to the pressure gradient limit obtained from the ideal, infinite-n stability codes, BALOO and 2DX, in all cases that have been examined. Predictions of a heuristic drift model for the heat flux width are also in qualitative agreement with the measurements. We obtained these results by using an improved high rep-rate and higher edge spatial resolution Thomson scattering system on DIII-D to measure the upstream electron temperature and density profiles. In order to compare theory and experiment, profiles of density, temperature, and pressure for both electrons and ions are needed as well values of these quantitities at the separatrix. We also developed a simple method to identify a proxy for the separatrix.

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Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); General Atomics, San Diego, CA (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: FC02-04ER54698; AC52-07NA27344; AC02-09CH11466

OSTI ID:: 1345540

Alternate ID(s):: OSTI ID: 1252220

Journal Information:: Journal of Nuclear Materials, Vol. 463, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 8 works

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Experimental study of heating scheme effect on the inner divertor power footprint widths in EAST lower single null discharges Deng, G. Z.; Xu, J. C.; Liu, X. Plasma Physics and Controlled Fusion, Vol. 60, Issue 4 https://doi.org/10.1088/1361-6587/aaa8c5	journal	February 2018

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