TRACT COMPUTER CODE APPLICATION IN THE ASSESSMENT OF SNF AND RW CLASS 1 RADIONUCLIDE COMPOSITIONS AND RADIATION CHARACTERISTICS

The article presents the results of computational studies addressing radionuclide compositions and radiation characteristics of spent nuclear fuel from WWER-440 and BN-600 reactor units performed using new computer code TRACT. These studies are performed to acquire basic information enabling further forecasts of RW Class 1 characteristics generated from the reprocessing of these fuel types. The calculations allowed to identify the characteristics of WWER-440 and BN-600 SNF considering various irradiation and storage conditions, including different burnup levels and pre-reprocessing cooling times. Such data will enable further evaluation of possible ranges describing the characteristics of RW Class 1.

Keywords: computer code, nuclide kinetics, spent nuclear fuel, radiation characteristics, energy release, pressurized water power reactor, sodium-cooled fast neutron reactor, radioactive waste, aluminum-phosphate glass.

Blokhin A. I., Blokhin P. A., Kazieva S. T. TRACT Computer Code Application in the Assessment of SNF and RW Class 1 Radionuclide Compositions and Radiation Characteristics. Radioactive waste, 2020, no. 4 (13), pp. 99—111. DOI: 10.25283/2587-9707-2020-4-99-111. (In Russian).