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Title: Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module

Abstract

Investigation of turbulent transport dynamics in scrape-off-layer (SOL) and divertor heat flux width prediction is performed for ITER. Both BOUT++ transport and BOUT++ turbulence codes are applied to capture the physics on different temporal scales. Simulations start with an ITER 15MA baseline scenario profile generated by CORSICA (Kim et al 2015 Paper ITER_D_R9T8J9 v1.1). In BOUT++ transport code, the plasma parameters ( n i, T i, T e) and radial electric () profiles are evolved to steady state. Here, the initial plasma profiles inside the separatrix are taken from CORSICA scenario studies. Transport coefficients are calculated by inverting the plasma profiles inside the separatrix.

Authors:
ORCiD logo [1];  [1];  [2];  [3];  [4]
  1. Peking Univ., Beijing (China); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dalian Univ. of Technology, Dalian (China)
  3. Univ. of Science and Technology of China, Hefei (China); General Atomics, San Diego, CA (United States)
  4. Harbin Inst. of Technology, Harbin (China)
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1568009
Report Number(s):
LLNL-JRNL-759268
Journal ID: ISSN 0029-5515; 947598
Grant/Contract Number:  
AC52-07NA27344
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Fusion
Additional Journal Information:
Journal Volume: 59; Journal Issue: 4; Journal ID: ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ITER; heat flux width; transport; drift; turbulence

Citation Formats

Li, Ze-Yu, Xu, X. Q., Li, Na-Mi, Chan, V. S., and Wang, Xiao-Gang. Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module. United States: N. p., 2019. Web. doi:10.1088/1741-4326/ab0184.
Li, Ze-Yu, Xu, X. Q., Li, Na-Mi, Chan, V. S., & Wang, Xiao-Gang. Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module. United States. doi:10.1088/1741-4326/ab0184.
Li, Ze-Yu, Xu, X. Q., Li, Na-Mi, Chan, V. S., and Wang, Xiao-Gang. Wed . "Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module". United States. doi:10.1088/1741-4326/ab0184.
@article{osti_1568009,
title = {Prediction of divertor heat flux width for ITER using BOUT++ transport and turbulence module},
author = {Li, Ze-Yu and Xu, X. Q. and Li, Na-Mi and Chan, V. S. and Wang, Xiao-Gang},
abstractNote = {Investigation of turbulent transport dynamics in scrape-off-layer (SOL) and divertor heat flux width prediction is performed for ITER. Both BOUT++ transport and BOUT++ turbulence codes are applied to capture the physics on different temporal scales. Simulations start with an ITER 15MA baseline scenario profile generated by CORSICA (Kim et al 2015 Paper ITER_D_R9T8J9 v1.1). In BOUT++ transport code, the plasma parameters (ni, Ti,Te) and radial electric () profiles are evolved to steady state. Here, the initial plasma profiles inside the separatrix are taken from CORSICA scenario studies. Transport coefficients are calculated by inverting the plasma profiles inside the separatrix.},
doi = {10.1088/1741-4326/ab0184},
journal = {Nuclear Fusion},
number = 4,
volume = 59,
place = {United States},
year = {2019},
month = {2}
}

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