Electromagnetic turbulence simulation of tokamak edge plasma dynamics and divertor heat load during thermal quench

Journal Article · 11 July 2023 · Nuclear Fusion

DOI: https://doi.org/10.1088/1741-4326/acdfe4 · OSTI ID:1989399

Zhu, Ben ; Xu, Xue-qiao; Tang, Xian-Zhu

Abstract The edge plasma turbulence and transport dynamics, as well as the divertor power loads during the thermal-quench phase of tokamak disruptions, are numerically investigated with BOUT++’s flux-driven six-field electromagnetic turbulence model. Here, transient yet intense particle and energy sources are applied at the pedestal top to mimic the plasma power drive at the edge induced by a core thermal collapse, which flattens the core temperature profile. Interesting features, such as surging of divertor heat load (up to 50 times) and broadening of heat-flux width (up to four times) on the outer-divertor target plate, are observed in the simulation, in qualitative agreement with experimental observations. The dramatic changes in divertor heat load and width are due to the enhanced plasma turbulence activities inside the separatrix. Two cross-field transport mechanisms, namely, the E  ×  B turbulent convection and the stochastic parallel advection/conduction, are identified to play important roles in this process. First, an elevated edge pressure gradient drives instabilities and subsequent turbulence in the entire pedestal region. The enhanced turbulence not only transports particles and energy radially across the separatrix via the E  ×  B convection, which causes the initial divertor heat-load burst, but it also induces amplified magnetic fluctuation $\tilde{B}$ . Once themagnetic fluctuation is large enough to break the magnetic flux surface, magnetic flutter effect provides an additional radial transport channel. In the late stage of our simulation, $|{\tilde{B}}_{\text{r}}/B_0|$ reaches to 10 ⁻⁴ level that completely breaks magnetic flux surfaces such that stochastic field lines are directly connecting pedestal top plasma to the divertor target plates or first wall, further contributing to the divertor heat-flux width broadening.

• Sponsoring Organization: USDOE
• Grant/Contract Number: 89233218CNA000001; AC02-05CH11231; AC52-07NA27344
• OSTI ID: 1989399
• Journal Information: Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 8 Vol. 63; ISSN 0029-5515
• Publisher: IOP PublishingCopyright Statement
• Country of Publication: IAEA
• Language: English