One of the important tasks in the field of mathematical modeling of research nuclear reactors is the verification of computational codes used for the calculation of neutron-physical parameters.
The MCU-PTR program is designed to simulate neutron and photon transport processes using analog and non-analog Monte-Carlo methods on multiprocessor computers using evaluated nuclear data in systems with three-dimensional geometry, taking into account changes in the isotopic composition of materials.
This article presents information on the verification and validation of the MCU-PTR program with the MCUDB50 constant library for a full-scale simulation of the IVV-2M research nuclear reactor. Validation was based on a comparison of MCU-PTR calculation results with experimental data obtained during the operation of the IVV-2M reactor.
A model of the IVV-2M research nuclear reactor was developed for calculations using the MCU-PTR program with the MCUDB50 databank, taking into account fuel burnup depth. Computational studies were used to validate the parameters of the spatial-temporal discretization of the computational models.
The experience gained from the validation procedure of the MCU-PTR computational code at the IVV-2M research nuclear reactor can be applied by specialists from other organizations whose activities involve software verification and certification, including for the purpose of aligning their activities with federal rules and regulations establishing requirements for the safe use of nuclear energy.
► Keywords: MCU-PTR program, research nuclear reactor, modeling, Monte-Carlo method, calculation, neutron-physical parameters, validation.
Article language: Russian. Pp. 5–24. [in Russian]. DOI: 10.26277/SECNRS.2026.119.1.001.
