Mathematical analysis of the main parameters of a spherical fuel cell for high-Temperature reactors

K. Karichev, A. Kudrov, S. Lavrinenko

Research output: Chapter in Book/Report/Conference proceedingConference contribution


The technology of modular high-Temperature nuclear reactors (VHTR), due to the high degree of safety and environmental friendliness, can provide a comprehensive supply of electricity and heat, as well as solve the actual problem of effective hydrogen generation. The purpose of this study is to analyze the possibility and prospects of using gas-cooled nuclear reactors in the energy area and primary production. In the article the algorithm of primary calculations of the main characteristics, such as: distribution of the neutron flux density in the reactor core (the volume of the nuclear reactor occupied by fuel elements) and the reflector along the radius; the critical radius of the nuclear reactor-the minimum radius of the reactor at which it supports a self-sustaining chain reaction of fuel nuclei; the volume of the nuclear reactor determined for the found critical radius of the reactor; the average density of the neutron flux in the volume of the nuclear reactor; macroscopic cross sections of the main interactions; average thermal power of a nuclear reactor. A comparative analysis of the results of the algorithm for different materials of fuel and reflector, as well as the percentage of fuel enrichment by the isotope of uranium-235 is made. As a result, it was found that the most suitable reflector is graphite because of its cost and safety as compared with beryllium. Uranium oxide is more effective than metallic uranium.

Original languageEnglish
Title of host publicationThermophysical Basis of Energy Technologies, TBET 2019
EditorsGeniy Kuznetsov, Dmitry Feoktistov, Evgeniya Orlova
PublisherAmerican Institute of Physics Inc.
ISBN (Electronic)9780735419636
Publication statusPublished - 13 Mar 2020
Event2019 Thermophysical Basis of Energy Technologies - Tomsk, Russian Federation
Duration: 9 Oct 201911 Oct 2019

Publication series

NameAIP Conference Proceedings
ISSN (Print)0094-243X
ISSN (Electronic)1551-7616


Conference2019 Thermophysical Basis of Energy Technologies
CountryRussian Federation

ASJC Scopus subject areas

  • Physics and Astronomy(all)

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