EDN: FQYFNZ
Authors & Affiliations
Gusev A.A., Ivanov D.T., Klimenko L.V.
National Research Centre “Kurchatov Institute”, Moscow, Russia
Gusev A.A. – Researcher. Contacts: 1, pl. Akademika Kurchatova, Moscow, Russia, 123182. Tel.: +7 (499) 196-71-00 (add. 64-23); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Ivanov D.T. – Laboratory Director.
Klimenko L.V. – Research Laboratory Assistant.
Abstract
This article outlines the development and optimization stages of the new B80GR program. Based on the Monte Carlo method, this program is designed for calculating gamma-ray transport through matter. It comprises several modules: pre-processing module for cross-sections, geometry module, collision module, radiation source definition module. B80GR employs a group-wise approach to simulate gamma-ray transport through matter and is designed to handle an arbitrary number of energy groups within the energy range up to 20 MeV. The preparation of the library of photoatomic interaction cross-sections for the developed program is performed using the processing code GRUCON, generating data in the TEMBR format. This library is based on a selected evaluated nuclear data library. The article also presents an analysis of comparative calculations for selected test models. These models consist of 50 cm radius spheres filled with one of the following materials: H2O, UO2, Zirconium alloy E635, B4C, AISI 321. For each material, calculations were performed using a monoenergetic gamma-ray source defined for each energy group. The source was located at the center of the sphere. Radiation currents (fluxes) were tallied on the surfaces of concentric spheres with varying radii: for H22O and B4C every 1 cm, for Zirconium alloy E635 and AISI 321: every 0.4 cm, for UO2: every 0.2 cm. Calculations were performed using both the B80GR program and MCNP4c2. The results obtained with both programs agree along the entire attenuation path length for all materials and across all energy groups.
Keywords
B80GR, gamma radiation, Monte Carlo method, multigroup method, SAPFIR software package, MCNP4c2, GRUCON, comparative calculations, nuclear fuel handling facilities
Article Text (PDF, in Russian)
References
- Tebin V.V., Borisenkov A.E. Kompleks programm SAPFIR-2006 dlya rascheta polnomasshtabnykh aktivnykh zon reaktorov VVER metodom Monte-Karlo [Complex of programs SAPFIRE-2006 for calculation of full-scale fissile regions of reactors VVER by a Monte-Carlo method]. Vestnik SGTU, 2006, vol. 4 (20), no. 5, pp. 94–100.
- Gomin E.A., Mayorov L.V. Programma VEPS dlya rascheta veroyatnostey pervykh stolknoveniy v trekhmernykh sistemakh [VEPS Program for Calculating First Collision Probabilities in Three-Dimensional Systems]. Preprint of the Institute of Atomic Energy No. 4207/5 – Preprint IAE No. 4207/5. Moscow, 1985.
- Briesmeister J.F. MCNP – A General Monte Carlo N-Particle Transport Code, Version 4C. Report LA-13709-M. Los Alamos National Laboratory, 2000.
- Carter L.L. et al. Monte Carlo Development in Los Alamos. LA-5903-MS, 1975.
- Sinitsa V.V., Rineiskiy A.A. GRUCON – A Package of Applied Computer Programs. Report INDC(CCCP)-344. Vienna: IAEA, 1993.
- Osipov V.K., Chistyakova V.A., Yudkevich M.S. TEMBR – format tekstovoy zapisi bibliotek
mnogogruppovykh konstant dlya rascheta reaktorov i zashchity [TEMBR is a text format for libraries of multigroup constants for reactor design and protection]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika i tekhnika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics and Engineering of Nuclear Reactors, 1982, vol. 27, issue 5, p. 62.
- Chernyaev A.P. Vzaimodeistvie ioniziruyushchego izlucheniya s veshchestvom [Interaction of ionizing radiation with matter]. Moscow, Fizmatlit Publ., 2004. 152 p.
- Photonuclear reactions. I, II. Ed. Costa S. and Schaerf С. (Lecture Notes in Physics, 61, 62.) Berlin – Heidelberg – New York: Springer-Verlag, 1977. Vol. Ι, 650 p., vol. ΙΙ, 301 p.
- Panin M.P. Modelirovanie perenosa izlucheniya. Uchebnoe posobie [Modeling of Radiation Transfer. Tutorial]. Moscow, MIFI Publ., 2008. 212 p.
- Munk M., Slaybaugh R. Review of Hybrid Methods for Deep-Penetration Neutron Transport. Nuclear Science and Engineering, 2019, vol. 193, no. 10, pp. 1055–1089.
- Mikhailov G.A. Nekotorye voprosy teorii metodov Monte-Karlo [Some Issues in the Theory of Monte Carlo Methods]. Novosibirsk, Iz-vo “Nauka” Sibirskoe otdelenie Publ., 1974. 144 p.
- Alekseev N.I., Veretenov V.V., Gurevich M.I. Geometricheskii modul' SCG-8 [Geometric Module
SCG-8]. Preprint IAE-5945/5, Moscow, 1996.
- Frank-Kamenetskiy A.D. Modelirovaniye trayektoriy neytronov pri raschete reaktorov metodom Monte-Karlo [Modeling Neutron Trajectories in Reactor Calculations Using the Monte Carlo Method]. Мoscow, Atomizdat Publ., 1978.
- Chadwick M.B. et al. ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections,
Covariances, Fission Product Yields and Decay Data. Nuclear Data Sheets, 2011, vol. 112, issue 12, рp. 2887–2996.
- Conlin J.L. A Compact ENDF (ACE) Formаt Specification. La-UR-19-29016. Available at: https://www.nndc.bnl.gov/endf-b8.0/ (accessed 04.01.2026).
UDC 621.039.58
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 2, 2:7