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This article summarizes the results of our research on the possibility of using a magnesium potassium phosphate (MPP) matrix to solve the problem of immobilization of radioactive waste (RW) generated during reprocessing of mixed uranium plutonium nitride spent nuclear fuel. We used CaCO3 as a surrogate of waste containing 14C, as well as an aqueous solution of 41.6% LiCl-52.9% KCl-5.5% CsCl as a surrogate of the spent electrolyte formed during the pyrochemical fuel reprocessing. The mechanical, radiation and hydrolytic stability of the obtained compounds were investigated. It was found that the compounds have a high compressive strength of 17– 26 MPa. The minimum carryover of carbon dioxide into the atmosphere during the synthesis and keeping of the samples for 14 days was noted no more than 3 wt%. It was found that the change of the matrix phase occurs during the irradiation by accelerated electrons during the accumulation of the absorbed dose of 108 Gy. In this case, the leaching rate of components of the compound including irradiated one corresponds to the current regulatory requirements for materials for RW immobilization. The differential leaching rate of Cs at 25 °C from monolithic samples containing LiCl-KCl-CsCl on the 91st day of samples contact with water was (5–11) × 10-5 g/(cm2·day) (according to GOST R 52126-2003 test), and was (4–29) × 10−7 g/(cm2∙day) on the 7th day at 90 °C from crushed samples (in accordance with PCT standard). The thermal stability of the compound containing LiCl-KCl-CsCl up to 450 °C was shown.

rad conference proceedings.

MAGNESIUM POTASSIUM PHOSPHATE MATRIX FOR THE IMMOBILIZATION OF RADIOACTIVE WASTE GENERATED DURING THE REPROCESSING OF MIXED URANIUM PLUTONIUM NITRIDE SPENT NUCLEAR FUEL