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Title: Edge turbulence and divertor heat flux width simulations of Alcator C-Mod discharges using an electromagnetic two-fluid model

Journal Article · · Nuclear Fusion
 [1];  [2];  [3];  [4];  [4]; ORCiD logo [4]; ORCiD logo [4];  [4];  [5];  [5];  [5]
  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. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  5. Univ. of Science and Technology of China, Hefei (China)

The BOUT++ code has been utilized in order to improve the understanding of the role of turbulent modes in controlling edge transport and resulting scaling of the scrape-off layer (SOL) heat flux width. For the C-Mod enhanced Dα (EDA) H-mode discharges, BOUT++ six-field two-fluid nonlinear simulations show a reasonable agree- ment of upstream turbulence and divertor target heat flux behavior: a) The simulated quasi-coherent modes (QCMs) show consistent characteristics of the frequency versus poloidal wave number spectra of the electromagnetic fluctuations when compared with experimental measurements: frequencies are around 60-120 kHz (experiment: about 70-110 kHz), kθ are around 2.0 cm₋1 which is similar to the Phase Contrast Imaging data; b) Linear spectrum analysis is consistent with the nonlinear phase relationship cal- culation which indicates the dominance of resistive-ballooning modes and drift-Alfven wave instabilities; c) The SOL heat flux width λq vs current Ip scaling is reproduced by turbulent transport: the simulations yield similar λq to experimental measurements within a factor of 2. Yet the magnitudes of divertor heat fluxes can be varied, depending on the physics models, sources and sinks, sheath boundary conditions, or flux limiting coefficient; d) Simple estimate by the "2-point model" for λq is consistent with simulation. Moreover, blobby turbulent spreading is confirmed for these relatively high Bp shots.

Research Organization:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE National Nuclear Security Administration (NNSA); USDOE Office of Science (SC), Fusion Energy Sciences (FES); National Natural Science Foundation of China (NSFC)
Grant/Contract Number:
AC52-07NA27344; FC02-99ER54512
OSTI ID:
1566032
Report Number(s):
LLNL-JRNL-722400; 868467; TRN: US2000962
Journal Information:
Nuclear Fusion, Vol. 57, Issue 11; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 34 works
Citation information provided by
Web of Science

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Cited By (6)

Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths journal May 2018
Experimental study of quasi-coherent mode using EAST tangential CO 2 laser collective scattering diagnostic in far-forward mode journal January 2019
Quasi-coherent mode simulation during inter-ELM period in HL-2A journal December 2018
Study of power width scaling in scrape-off layer with 2D electrostatic turbulence code based on EAST L-mode discharges journal April 2019
Impact of divertor plasma parameters on characteristics of current-convective turbulence under DIII-D-like detached conditions journal December 2019
Simulations of divertor heat flux width using transport code with cross-field drifts under the BOUT++ framework journal January 2020

Figures / Tables (23)


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