VALIDATION OF NUCLIDE KINETICS CODE TRACT FOR THE ASSESSMENT OF SNF AND RW RADIATION CHARACTERISTICS

The article presents a verification matrix for the TRACT code designed for nuclide kinetics calculations and demonstrates code validation results based on data from reactor experiments. It provides recommendations regarding future experimental SNF studies considered important in terms of assessing the long-term storage and disposal safety of SNF and RW generated from SNF reprocessing.

Keywords: calculation code, nuclide kinetics, spent nuclear fuel, radiation characteristics, energy release, pressurized water power reactor, verification, validation, reactor, radioactive waste.

Blokhin A. I., Blokhin P. A., Kazieva S. T., Sipachev I. V. Validation of Nuclide Kinetics Code TRACT for the Assessment of SNF and RW Radiation Characteristics. Radioactive Waste, 2022, no. 4 (21), pp. 48—57. DOI: 10.25283/2587-9707-2022-4-48-57. (In Russian).