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Simulations of NSTX with a Liquid Lithium Divertor Module
Author(s) -
Stotler D. P.,
Maingi R.,
Zakharov L.E.,
Kugel H.W.,
Pigarov A.Yu.,
Rognlien T.D.,
Soukhanovskii V. A.
Publication year - 2010
Publication title -
contributions to plasma physics
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.531
H-Index - 47
eISSN - 1521-3986
pISSN - 0863-1042
DOI - 10.1002/ctpp.201010060
Subject(s) - divertor , lithium (medication) , nuclear engineering , plasma , heat flux , materials science , heat transfer , computational physics , mechanics , physics , nuclear physics , tokamak , medicine , engineering , endocrinology
A strategy to develop self‐consistent simulations of the behavior of lithium in the Liquid Lithium Divertor (LLD) module to be installed in NSTX is described. In this initial stage of the plan, the UEDGE edge plasma transport code is used to simulate an existing NSTX shot, with UEDGE's transport coefficients set using midplane and divertor diagnostic data. The LLD is incorporated into the simulations as a reduction in the recycling coefficient over the outer divertor. Heat transfer calculations performed using the resulting heat flux profiles provide preliminary estimates on operating limits for the LLD as well as input data for subsequent steps in the LLD modeling effort (© 2010 WILEY‐VCH Verlag GmbH & Co. KGaA, Weinheim)

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