simulation of electric fields in small size divertor tokamak plasma edge电场的模拟小尺寸偏滤器托卡马克等离子体边缘.pdfVIP

Energy and Power Engineering, 2010, 39-45 doi:10.4236/epe.2010.21007 Published Online February 2010 (/journal/epe) Simulation of Electric Fields in Small Size Divertor Tokamak Plasma Edge A. H. BEKHEIT Plasma Nuclear Fusion Department, Nuclear Research Centre, Atomic Energy Authority, Cairo, Egypt Email : amrbekheitga@ Abstract: The fluid simulation of Small Size Divertor Tokamak (SSDT) plasma edge by the B2-SOLPS5.0 2D [1] transport code gives the following results: First, in the vicinity of separatrix the radial electric field result is not close to the neoclassical electric field. Second, the shear of radial electric field is independent on plasma parameters. Third, switching on poloidal drifts (E×B and diamagnetic drifts) leads to asymmetric par- allel and poloidal fluxes from outer to inner plates and upper part of SOL for normal direction of toroidal magnetic field. Fourth, for the normal direction of toroidal magnetic, the radial electric field of SSDT is af- fected by the variation in temperature heating of plasma. Fifth, the parallel flux is directed from inner to outer plate in case of discharge without neutral beam injection (NBI). Keywords: electric field, transport codes, divertor tokamak 1. Introduction the applicability of the fluid equations. On the basis of simulation for different power of additional heating, A regime of improved confinement is extremely impor- plasma densities, toroidal rotation velocities and mag- tant for the operation of a thermonuclear reactor. A tran-