Study of Neutronic Processes Determining the Nature of Nuclear Heating of Materials in the Impulse Graphite Reactor

Abstract

Tightening the requirements for methodological support for in-pile experiments determines the need to improve the quality of predicting parameters of irradiated experimental devices that are important from a safety point of view. To qualitatively predict the temperature of device elements during irradiation in the IGR reactor, this paper presents an analysis of the radiation heating mechanisms under the influence of neutron and gamma fields of the reactor. Calculations were conducted to determine the contribution of various neutronic processes to the resulting nuclear heating of samples of structural materials during their planned irradiation in the IGR reactor, and the volumetric distribution of energy release in samples of structural materials was determined.