Open AccessPrediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module
Author(s) -
Zeyu Li,
X. Q. Xu,
Nami Li,
V. S. Chan,
Xiaogang Wang
Publication year - 2019
Publication title -
nuclear fusion
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 1.774
H-Index - 120
eISSN - 1741-4326
pISSN - 0029-5515
DOI - 10.1088/1741-4326/ab0184
Subject(s) - divertor , pedestal , turbulence , thermal diffusivity , physics , heat flux , plasma , mechanics , flux (metallurgy) , tokamak , computational physics , heat transfer , nuclear physics , materials science , thermodynamics , metallurgy , archaeology , history
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