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.; Terry, J. L.; Sun, J. Z.; Wang, D. Z.

doi:10.1063/1.5126884

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

Journal Article · Mon Jan 13 00:00:00 EST 2020 · AIP Advances

DOI:https://doi.org/10.1063/1.5126884· OSTI ID:1897177

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Dalian Univ. of Technology (China); Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); OSTI
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center
Dalian Univ. of Technology (China)

The fluid transport code [trans-electric field (Er) module] under the BOUT++ framework has been used to simulate divertor heat flux width and boundary Er with all drifts and the sheath potential in the scrape-off layer. The calculated steady state radial Er in the pedestal region has been compared with that of experimental measurements from the Alcator C-Mod tokamak. The magnitude and shape of Er are similar to those of the experimental data. In order to understand the relative role of cross-field drifts vs turbulent transport in setting the heat flux width, four C-Mod enhanced D_α H-mode discharges with a lower single null divertor configuration should be simulated. BOUT++ transport simulations with cross-field drifts included yield similar heat flux width λ_q to that of experimental measurements (within a factor of 2) from both the probe and the surface thermocouple diagnostics and show a similar trend with plasma current to that of the Eich experimental scaling. The simulations show that both drifts and turbulent transport compete to determine the heat flux width. The magnetic drifts play a dominant role in setting the divertor heat-flux width, while the E × B drift decreases the heat flux width by 10%–25%, leading to improved agreement with the experiment relative to Goldston’s model. A turbulence diffusivity scan ($${\chi}$$_⊥) identifies two distinct regimes: a drift dominant regime when $${\chi }$$_⊥ is small and a turbulence dominant regime when $${\chi}$$_⊥ is large. The Goldston heuristic drift model yields a lower limit of the width λ_q.

View Accepted Manuscript (DOE)

Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States); Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States). Plasma Science and Fusion Center

Sponsoring Organization:: National Key Research and Development Program of China; National Natural Science Foundation of China (NSFC); USDOE; USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC52-07NA27344; SC0014264

OSTI ID:: 1897177

Alternate ID(s):: OSTI ID: 1582494

Journal Information:: AIP Advances, Journal Name: AIP Advances Journal Issue: 1 Vol. 10; ISSN 2158-3226

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

Country of Publication:: United States

Language:: English

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