Currently reconstruction is initiated on the T-15 tokamak at the Institute of Tokamak Physics, NRC “Kurchatov Institute”. The purpose of the reconstruction is to build the facility with a small aspect ratio , elongated cross-section and the divertor with a major radius of 1.67 m, long plasma current pulse of 2 MA up to 10 s and powerful auxiliary plasma heating (up to 15 MW). The facility is intended for demonstration of the plasma steady-state burning with high parameters for physics research to support the ITER program and program for development of volumetric neutron sources. The reconstruction involves replacement of the existing superconducting TF magnet system and cryoresistive PF system by the “warm” system. The developed magnet system provides the above-mentioned tokamak parameters. The magnet system of the new facility use of the T-10 and T-15 infrastructure, thus essentially determining the choice of its main parameters.

The objective of the present paper is to investigate the vertical stability of the plasma column in the project of the T - 15M tokamak. It has been shown that a passive stabilizing structure consisting of a vacuum vessel and two (upper and lower) passive coils is capable of providing vertical stability of the plasma column.

The method of subregions. first used for the design of circular flexible plates free at the contour, yields results sufficiently accurate for practical purposes.