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

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.
Authors:
 [1] ;  [1] ;  [2] ;  [2] ;  [1] ;  [3] ;  [4] ;  [3] ;  [5] ;  [5]
  1. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  2. General Atomics, San Diego, CA (United States)
  3. Univ. of Toronto, ON (Canada). Inst. for Aerospace Studies
  4. Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
  5. Lodestar Research Corp., Boulder, CO (United States)
Publication Date:
OSTI Identifier:
1345540
Grant/Contract Number:
FC02-04ER54698; AC52-07NA27344; AC02-09CH11466; AC52-07NA27344, DE-FC02-04ER54698, and DE-AC02-09CH11466
Type:
Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 463; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Research Org:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS