Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths

Chen, B.; Xu, X. Q.; Xia, T. Y.; Li, N. M.; Porkolab, M.; Edlund, E.; LaBombard, B.; Terry, J.; Hughes, J. W.; Ye, M. Y.; Wan, Y. X.

doi:10.1063/1.5016582

Title: Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths

Journal Article · Wed May 09 00:00:00 EDT 2018 · Physics of Plasmas

DOI:https://doi.org/10.1063/1.5016582· OSTI ID:1543851

Chen, B. ^[1];

^[2];

^[3]; Li, N. M. ^[4]; Porkolab, M. ^[5]; Edlund, E. ^[5]; LaBombard, B. ^[5];

^[5];

^[5]; Ye, M. Y. ^[6]; Wan, Y. X. ^[6]

Univ. of Science and Technology of China, Hefei (China); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chinese Academy of Sciences (CAS), Hefei (China)
Dalian Univ. of Technology (China)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Univ. of Science and Technology of China, Hefei (China)

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Research Organization:: Lawrence Berkeley National Laboratory (LBNL), Berkeley, CA (United States). National Energy Research Scientific Computing Center (NERSC); Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES); National Natural Science Foundation of China (NSFC); USDOE National Nuclear Security Administration (NNSA)

Grant/Contract Number:: FC02-99ER54512; SC0014264; AC52-7NA27344; AC52-07NA27344

OSTI ID:: 1543851

Alternate ID(s):: OSTI ID: 1436555; OSTI ID: 1566016

Report Number(s):: LLNL-JRNL-742019

Journal Information:: Physics of Plasmas, Vol. 25, Issue 5; ISSN 1070-664X

Publisher:: American Institute of Physics (AIP)Copyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 18 works

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Cited By (4)

Simulations of divertor heat flux width using transport code with cross-field drifts under the BOUT++ framework Li, N. M.; Xu, X. Q.; Hughes, J. W. AIP Advances, Vol. 10, Issue 1 https://doi.org/10.1063/1.5126884	journal	January 2020
Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module Li, Ze-Yu; Xu, X. Q.; Li, Na-Mi Nuclear Fusion, Vol. 59, Issue 4 https://doi.org/10.1088/1741-4326/ab0184	journal	February 2019
The impact of edge radial electric fields on edge–scrape-off layer coupling in the TJ-II stellarator Grenfell, G.; van Milligen, B. Ph.; Losada, U. Nuclear Fusion, Vol. 60, Issue 1 https://doi.org/10.1088/1741-4326/ab538c	journal	November 2019
Nonlinear simulation and energy analysis of the EAST coherent mode Huang, Y. Q.; Xia, T. Y.; Xu, X. Q. Nuclear Fusion, Vol. 60, Issue 2 https://doi.org/10.1088/1741-4326/ab5e73	journal	January 2020

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