Результаты численного моделирования термогазодинамики кассеты твэлов ядерного реактора на быстрых нейтронах

Abstract

В статье рассматриваются некоторые результаты вычислительных экспериментов, проведенных автором с помощью авторской программы ПЭВМ. Анализируются успешные и аварийные результаты, возникшие при численном моделировании газодинамики как в активной зоне, так и в коллекторах кассеты из 4 и 8 тепловыделяющих элементов.

The paper presents the results of computational experiments obtained by an authorial program for designing gas dynamics, which takes place in the active zone of fast-neutron nuclear reactor with helium coolant-moderator and its adjoining collectors. The Generation IV International Forum refers the reactors of such type to the 4-th generation nuclear energy systems. Using helium as coolant-moderator in such reactors is extremely perspective, but implementation of such a project faces many difficulties. The methods and algorithm for joint solving of gas dynamic problem in the fuel elements and their adjoining collectors were developed in the author’s recent paper published in the Bulletin of V. N. Karazin Kharkiv National University, series: "Mathematics, Applied Mathematics, and Mechanics", 2018, vol. 88. In the present paper an example of successful numerical modeling of gas dynamic process in a fuel slug consisting of 4 active zones is proposed. In particular, the plots of changes in time of consumption rate of both cool and heated coolant-moderator at the entrance and exit of the fuel slug are given. The dependence on time of temperature changes at the fuel element exit is also plotted. The plots of isobar distribution in the fuel elements at specific times as well as the trajectories of free vortices in the collectors are shown. At the end of the paper the results of a computational experiment resulting in an emergency situation in a fuel slug consisting of 8 fuel elements and its causes are discussed.