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

Authors:
 [1]; ORCiD logo [2]; ORCiD logo [3];  [4];  [5];  [5];  [5]; ORCiD logo [5]; ORCiD logo [5];  [6];  [6]
  1. Univ. of Science and Technology of China, Hefei (China); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  3. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chinese Academy of Sciences (CAS), Hefei (China)
  4. Dalian Univ. of Technology (China)
  5. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  6. Univ. of Science and Technology of China, Hefei (China)
Publication Date:
Research Org.:
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 Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES); National Natural Science Foundation of China (NSFC); USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1543851
Alternate Identifier(s):
OSTI ID: 1436555; OSTI ID: 1566016
Report Number(s):
LLNL-JRNL-742019
Journal ID: ISSN 1070-664X
Grant/Contract Number:  
FC02-99ER54512; SC0014264; AC52-7NA27344; AC52-07NA27344
Resource Type:
Accepted Manuscript
Journal Name:
Physics of Plasmas
Additional Journal Information:
Journal Volume: 25; Journal Issue: 5; Journal ID: ISSN 1070-664X
Publisher:
American Institute of Physics (AIP)
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats

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., and Wan, Y. X. Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths. United States: N. p., 2018. Web. doi:10.1063/1.5016582.
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. Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths. United States. https://doi.org/10.1063/1.5016582
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., and Wan, Y. X. Wed . "Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths". United States. https://doi.org/10.1063/1.5016582. https://www.osti.gov/servlets/purl/1543851.
@article{osti_1543851,
title = {Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths},
author = {Chen, B. and Xu, X. Q. and Xia, T. Y. and Li, N. M. and Porkolab, M. and Edlund, E. and LaBombard, B. and Terry, J. and Hughes, J. W. and Ye, M. Y. and Wan, Y. X.},
abstractNote = {},
doi = {10.1063/1.5016582},
journal = {Physics of Plasmas},
number = 5,
volume = 25,
place = {United States},
year = {Wed May 09 00:00:00 EDT 2018},
month = {Wed May 09 00:00:00 EDT 2018}
}

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Cited by: 18 works
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Works referencing / citing this record:

Simulations of divertor heat flux width using transport code with cross-field drifts under the BOUT++ framework
journal, January 2020

  • Li, N. M.; Xu, X. Q.; Hughes, J. W.
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Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module
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The impact of edge radial electric fields on edge–scrape-off layer coupling in the TJ-II stellarator
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Nonlinear simulation and energy analysis of the EAST coherent mode
journal, January 2020