THE NUMERICAL CODE RPB FOR DETERMINATION PLASMA BOUNDARY FROM MAGNETIC MEASUREMENTS (MODULE OF PROGRAM LIBRARY "VIRTUAL TOKAMAK")
The diagnostics of plasma boundary using magnetic measurements is one of the urgent problems in physics of Tokamak with a divertor, as it allows you to control the development of vertical instability. The article provides with a brief description of the standard code of RPB (Reconstruction of Plasma Boundary) for the calculation of the boundary plasma in a Tokamak device using the results of the ex- ternal magnetic measurements. This task is vital for the solution of the inverse problem of the MHD equilibrium of a toroidal plasma, based on the two-dimensional elliptic Grad-Shafranov equation, with additional conditions of the Cauchy type on a contour of observa- tion. Measurements of the poloidal magnetic field and stream function, as well as the current values in the poloidal magnetic system and the induced currents in the structural elements of the installation were used as the initial data. The method of regularized integral equa- tions is used for the numerical solution of the problem. Description of the RPB program interface is provided. Various features of the program in different experimental conditions are shown on the example of the direct problem of plasma equilibrium for the KTM device. This code is one of the modules of the «Virtual Tokamak» library.