EDN: TZTPTL
Authors & Affiliations
Kruglikov A.E.1, Shchurovskaya M.V.1, Volkov Yu.N.1, Nevinitsa V.A.2, Fomichenko P.A.2, Grol A.V.2
1 National Research Nuclear University “MEPHI”, Moscow, Russia
2 National Research Centre “Kurchatov Institute”, Moscow, Russia
Kruglikov A.E.1 – Research Engineer, Assistant. Contacts: 31, Kashirskoe sh., Moscow, 115409, Russia. Tel.: +7 (965) 377-27-64; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Shchurovskaya M.V.1 – Leading Researcher, Cand. Sci. (Tech.).
Volkov Yu.N.1 – Assistant Professor, Cand. Sci. (Tech.).
Nevinitsa V.A.2 – Head of Department, Cand. Sci. (Tech.)
Fomichenko P.A.2 – Deputy Head of the Complex for Science
Grol A.V. – Deputy Head of the Department.
Abstract
A number of international benchmarks are used to verify software tools used for neutron-physical calculations of high-temperature nuclear reactors. One of these features is the use of fuel in the form of microparticles and a graphite reflector. The paper presents for the first time the results of calculations using the MCU program for experiments carried out at the CNPS reactor in the second half of the 1980s. The reactor core consists of compacts with microfuels, as well as a graphite moderator and reflectors, which makes this reactor representative in terms of software verification for determining the neutron-physical parameters of HTGR reactors. The paper provides a description of the benchmark, and also considers previous calculations. The results of calculations of critical states, as well as physical weights of various replaceable components of the reactor are given. According to the simulation results, the MCU program shows good agreement with both experimental data and previous calculations performed using the MCNP and McCARD Monte Carlo programs.
Keywords
high-temperature gas-cooled reactor, neutronic calculations, experimental data, Monte Carlo method, microfuel, graphite reflector, verification, MCU-HTR
Article Text (PDF, in Russian)
References
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UDC 621.039.5
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, no. 4, 1:4
