A Simple Hybrid Model for SOL, Pedestal and Core Tokamak Plasmas

In this paper, the divertor heat flux density profile is being discussed. The simple robust model, dealing with core, pedestal and edge plasmas was improved. The model was applied to the ITER basic regime. Heat flux density was estimated for two different cases of heat flux SOL width of ITER. In the...

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Published inContributions to plasma physics (1988) Vol. 54; no. 4-6; pp. 368 - 372
Main Authors Bykov, A. S., Sergeev, V. Yu, Kuteev, B.V.
Format Journal Article
LanguageEnglish
Published Berlin WILEY-VCH Verlag 01.06.2014
WILEY‐VCH Verlag
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Summary:In this paper, the divertor heat flux density profile is being discussed. The simple robust model, dealing with core, pedestal and edge plasmas was improved. The model was applied to the ITER basic regime. Heat flux density was estimated for two different cases of heat flux SOL width of ITER. In the case of wide 2 cm SOL, the peak divertor heat flux density is under technological limit of 10 MW/m2. In the case of quite narrow 1 mm width SOL, peak divertor heat flux density exceeds this limit by several times and detached divertor regimes should be considered. (© 2014 WILEY‐VCH Verlag GmbH & Co. KGaA, Weinheim)
Bibliography:ark:/67375/WNG-CWWBRHQK-R
ArticleID:CTPP201410030
istex:7C2E6B5DC6DD1C86E2E3D7ED6064BE2164AD7013
ObjectType-Article-1
SourceType-Scholarly Journals-1
ObjectType-Feature-2
content type line 23
ISSN:0863-1042
1521-3986
DOI:10.1002/ctpp.201410030