DEVELOPMENT OF AN ALGORITHM FOR ESTIMATING THE RADIONUCLIDE COMPOSITION OF VITRIFIED HLW OF FSUE “PA “MAYAK” FOR THE PURPOSE OF THEIR SAFE DISPOSAL

A method for a calculation the activity of relevant radionuclides in vitrified RW Class 1 FSUE "PA Mayak" is developed. This method is supposed to be used for a safety case of radioactive waste disposal in geological formations. The algorithm is based on the calculated isotopic composition of spent nuclear fuel data, which was determined on the basis of its characteristics (initial enrichment at 235 U, burnup and cooling time after irradiation), and parameters of technological a redistribution of radionuclides at materials streams at various stages of SNF reprocessing.

 

Key words: nuclear spent fuel, radioactive waste, alumophosphate glass, vitrification, relevant radionuclide.

Remizov M. B., Kozlov P. V., Borisenko V. P., Dementeva I. I., Blokhin P. A., Samoylov A. A. Development of an Algorithm for Estimating the Radionuclide Composition of Vitrified HLW of FSUE “PA “Mayak” for the Purpose of Their Safe Disposal. Radioactive Waste, 2018, no. 3 (4), pp. 102—110. (In Russian).