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Title: Nonlinear fluid simulation of particle and heat fluxes during burst of ELMs on DIII-D with BOUT++ code [Fluid Simulation of Particle and Heat Fluxes during Burst of ELMs on DIID with BOUT++ code]

Journal Article · · Nuclear Fusion
 [1];  [2]
  1. Chinese Academy of Sciences (CAS), Hefei (China). Inst. of Plasma Physics
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

In order to study the distribution and evolution of the transient particle and heat fluxes during edge-localized mode (ELM) bursts, a BOUT++ six-field two-fluid model based on the Braginskii equations with non-ideal physics effects is used to simulate pedestal collapse in divertor geometry. We used the profiles from the DIII-D H-mode discharge #144382 with fast target heat flux measurements as the initial conditions for the simulations. Moreover, a flux-limited parallel thermal conduction is used with three values of the flux-limiting coefficient $${{\alpha}_{j}}$$ , free streaming model with $${{\alpha}_{j}}=1$$ , sheath-limit with $${{\alpha}_{j}}=0.05$$ , and one value in between. The studies show that a 20 times increase in $${{\alpha}_{j}}$$ leads to ~6 times increase in the heat flux amplitude to both the inner and outer targets, and the widths of the fluxes are also expanded. The sheath-limit model of flux-limiting coefficient is found to be the most appropriate one, which shows ELM sizes close to the measurements. The evolution of the density profile during the burst of ELMs of DIII-D discharge #144382 is simulated, and the collapse in width and depth of $${{n}_{\text{e}}}$$ are reproduced at different time steps. The growing process of the profiles for the heat flux at divertor targets during the burst of ELMs measured by IRTV (infrared television) is also reproduced by this model. The widths of heat fluxes towards targets are a little narrower, and the peak amplitudes are twice the measurements possibly due to the lack of a model of divertor radiation which can effectively reduce the heat fluxes. The magnetic flutter combined with parallel thermal conduction is found to be able to increase the total heat loss by around 33% since the magnetic flutter terms provide the additional conductive heat transport in the radial direction. Finally, the heat flux profile at both the inner and outer targets is obviously broadened by magnetic flutter. The lobe structures near the X-point at LFS are both broadened and elongated due to the magnetic flutter.

Research Organization:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Organization:
USDOE Office of Science (SC), Fusion Energy Sciences (FES)
Grant/Contract Number:
AC52-07NA27344
OSTI ID:
1321430
Report Number(s):
LLNL-JRNL-665624
Journal Information:
Nuclear Fusion, Vol. 55, Issue 11; ISSN 0029-5515
Publisher:
IOP ScienceCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 39 works
Citation information provided by
Web of Science

References (19)

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Cited By (6)

Electron parallel closures for the 3 + 1 fluid model journal March 2018
Progress towards modeling tokamak boundary plasma turbulence and understanding its role in setting divertor heat flux widths journal May 2018
Impact of bootstrap current and Landau-fluid closure on ELM crashes and transport journal May 2018
Quasi-coherent mode simulation during inter-ELM period in HL-2A journal December 2018
Self-consistent simulation of transport and turbulence in tokamak edge plasma by coupling SOLPS-ITER and BOUT++ journal January 2019
Simulations of divertor heat flux width using transport code with cross-field drifts under the BOUT++ framework journal January 2020

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