Applied mathematics

One-dimensional neutral transport modelling in a tokamak

A. A. Kozhurin^a, M. L. Dubrov^b, V. E. Zhogolev^a, R. R. Khayrutdinov^a, V. E. Lukash^a, A. A. Kavin^c, R. R. Andrianova<sup>a

a</sup> National Research Centre “Kurchatov Institute”, 1, Akademika Kurchatova pl., Moscow, 123182, Russian Federation
^b ITER Organization, CS 90 046, Route de Vinon-sur-Verdon, St. Paul Lez Durance Cedex, 13067, France
^c D. V. Efremov Institute of Electrophysical Apparatus, 3, Doroga na Metallostroy, St. Petersburg, 196641, Russian Federation

Abstract: Neutral transport models in tokamak plasmas for expanding functionality of the DINA code have been numerically implemented and their efficiencies have been estimated: a new two-dimensional Monte Carlo code MCN-2D, the reduced kinetic models of Yu. N. Dnestrovskii with monoenergetic distributions of primary neutrals and ions and the diffusion model. Monte Carlo models have been reviewed. Monte Carlo code EIRENE calculation results are selected as referenced neutral parameters profiles. It is shown that the reduced kinetic model in the flat geometry can be used in fast calculations with applicability conditions are satisfied. The presented diffusion model yields significant deviations in the energy balance. For more accurate calculations it is proposed to use MCN-2D code, which will be able to self-consistently calculate neutral transport over core and edge plasmas taking into account a plasma column shape or the cylindrical version of the reduced kinetic model.

Keywords: transport processes, neutrals, tokamak, DINA code, Monte Carlo method.

UDC: 533.1, 533.9.01

MSC: 90C90

Received: October 21, 2024
Accepted: December 12, 2024

DOI: 10.21638/spbu10.2025.103