Determination of the Radionuclide Composition of the Cesium–Strontium Fraction of High-Level Waste from Spent Nuclear Fuel Reprocessing

Abstract

Procedures were developed for measuring and calculating the radionuclide composition of the cesium–strontium fraction of radioactive waste from spent nuclear fuel reprocessing. The optimum conditions for recovering specific components and separating them from components interfering with their determination were found. The content of the following controlled radionuclides was determined experimentally: ¹⁴С, ⁹⁰Sr, ⁹⁹Tc, ¹²⁶Sn, ¹²⁹I, ^135,137Cs, ^{234–236,238}U, ^238–242Pu, ²³⁷Np, ^241,243Am, and ^244–246Cm. The content of ⁶³Ni, ⁹³Zr, ⁹⁴Nb, ¹⁵¹Sm, and ^242mAm was determined by calculations. The radionuclide composition was determined in the solution before solidification of the cesium–strontium fraction. The composition of the solidified cesium–strontium fraction in the form of the borosilicate glass was determined by the calculation from the activity concentrations of the radionuclides in the solution before solidification and process characteristics (solution volume, glass frit weight, separation factors, and factors of incorporation into the glass).