Author(s)

J. Sakellaris

Abstract

Next to the experimental approach of phenomena concerning plasma and plasma facing components of a tokamak another approach was adopted in this paper, a numerical modelling one. The study was done using CARIDDI, which is a 3D integral code for the eddy current density J, the problem is solved by computing at every edge of the finite element mesh the projection of a vector, the current vector potential T, whose uniqueness can be demonstrated mathematically by appropriately using the notions of tree and co-tree formed by branches of a graph, according to graph theory. A plasma is considered to be a toroidal conductor with an elliptical or rectangular cross-section. The section is subdivided into elements and the plasma current is carried in each single element by a filament, placed in its center. Keywords: modeling, tokamak, plasma equilibria, computational electromagnetic environment. 1 Introduction Controlled Thermonuclear Fusion technology has advanced rapidly during the last few years. The progress in the design and R&D activity undertaken in the Russian Federation in the period after completion of the ITER EDA is considerable. For the last 3 years, since 2001 FDR, the ITER design has been evolved in detail to resolve issues, to reduce costs, to define details and to prepare the procurement specifications for long-term items. During the ITER Transitional Arrangements (ITA) phase (2003–2004) the Design and R&D activity in the Russian Federation has been redirected and mainly concentrated on items in accordance

Keywords

modeling, tokamak, plasma equilibria, computational electromagnetic environment.