Abstract
Asymmetries between the divertor legs of small size divertor (SSD) tokamak plasma edge are noticed to reverse when the direction of toroidal magnetic field is reversed. In the present paper the small size divertor tokamak plasma edge under effect of toroidal magnetic field reversal is simulated by B2SOLPS0.5.2D fluid transport code. The simulation demonstrate the following results: 1) Parallel (toroidal) flow flux and Mach number up to 0.6 at higher plasma density reverse with reverse toroidal magnetic direction in the edge plasma of small size divertor tokamak. 2) The radial electric field is toroidal magnetic direction independence in edge plasma of small size divertor tokamak. 3) For normal and reverse toroidal magnetic field, the strong ITB is located between the positions of the maximum and minimum values of the radial electric field shear. 4) Simulation result shows that, the structure of radial electric field at high field side (HFS) and low field side (LFS) is different. This difference result from the change in the parallel flux flows in the scrape off layer (SOL) to plasma core through separatrix. 5) At a region of strong radial electric field shear, a large reduction of poloidal rotation was observed. 6) The poloidal rotation is toroidal magnetic field direction dependence.
Highlights
As a general trend, in single null divertor plasma, the in-out asymmetries in power and particle profile have long been observed between the divertor legs [1]
3) For normal and reverse toroidal magnetic field, the strong ITB is located between the positions of the maximum and minimum values of the radial electric field shear
We focus on the study of the of the reverse toroidal magnetic field direction on the edge plasma of small size divertor tokamak using 2-D SOLPS0.5 fluid transport code [1,4]; including the calculation of the radial electric field Er
Summary
10) Study the Material testing 11) The SSD tokomak experiment provides the possibility to study equilibrium, and the (resistive) MHD behavior of low-beta tokamak plasmas. 12) It will provide a very good opportunity in the future for students and young scientists to become acquainted with modern techniques the physics underlying the fusion research. 10) Study the Material testing 11) The SSD tokomak experiment provides the possibility to study equilibrium, and the (resistive) MHD behavior of low-beta tokamak plasmas. A fast and unproblematic exchange of magnetic divertors with different materials is possible and their influence on the plasma state can be examined. The small size divertor (SSD) tokamak has a lot of application to study the following subjects [5]: 1) Study of plasma–surface interaction processes. 3) Influence of wall conditioning (Carbonisation, boronisation, siliconisation etc) 4) Fluctuation measurements, in particular by probes 5) Study the transport processes in plasma (transport theory ) 6) Study spectroscopic analysis of impurities transport in plasma 7) Study the physics of edge plasma 8) Study the transition from low to high confinement (L-H) transition The small size divertor (SSD) tokamak has a lot of application to study the following subjects [5]: 1) Study of plasma–surface interaction processes. 2) Compatibility tests of divertor material and plasma. 3) Influence of wall conditioning (Carbonisation, boronisation, siliconisation etc) 4) Fluctuation measurements, in particular by probes 5) Study the transport processes in plasma (transport theory ) 6) Study spectroscopic analysis of impurities transport in plasma 7) Study the physics of edge plasma 8) Study the transition from low to high confinement (L-H) transition
Sign-in/Register to view highlights & summary Sign-in/Register to access full text options 
Free) 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a call
