Dynamical simulations of boundary plasma turbulence in divertor geometry

Physics

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Scientific paper

Direct comparisons between numerical simulations and the measured plasma fluctuations and transport are presented by performing nonlinear two-fluid simulations with the BOUT code (Xu X Q and Cohen R H 1998 Contrib. Plasma Phys. 38 158). BOUT models boundary-plasma turbulence in a realistic divertor geometry using modified Braginskii equations for plasma vorticity, density (ni), electron and ion temperature (Te, Ti) and parallel momenta. The BOUT code solves for the plasma fluid equations in a 3D toroidal segment, including the region somewhat inside the separatrix and extending into the scrape-off layer; the private flux region is also included. In this paper, the physics of resistive X-point turbulence and its relation to flow shear generation is discussed. We present comparisons between the boundary plasma turbulence observed in the BOUT code and experiments on DIII-D (Luxon J L et al 1986 Int. Conf. on Plasma Physics and Controlled Nuclear Fusion (Vienna: IAEA) p 159), the National Spherical Torus Experiment (Peng Y-K M 2000 Phys. Plasmas 7 1681), and C-Mod (Hutchinson I H et al 1994 Phys. Plasmas 1 1511). In an L-mode discharge in the DIII-D tokamak, both BOUT simulations and beam emission spectroscopy show a similar flow pattern and blob size across the last closed flux surface. In an L-mode discharge, both BOUT simulations and gas puff imaging show similar filament structures along the field line and similar frequency spectrum at the outboard midplane. In simulations of the quasi-coherent mode in the EDA regime of C-Mod, the particle flux measured from BOUT simulation is consistent with Langmuir probe measurements on C-Mod at the midplane near the separatrix. The qualitative comparisons thus indicate that BOUT contains much of the relevant physics for boundary plasma turbulence in the experimentally relevant X-point divertor geometry of present-day tokamaks and spherical tori.

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