PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY
Series: Nuclear and Reactor Constants

since 1971

Русский (РФ)

ISSN 2414-1038 (online)

B80GR GAMMA QUANTA TRANSPORT PROGRAM WITHIN THE SAPFIR SOFTWARE PACKAGE

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

UDC 621.039.58

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 2, 2:7