Study of sorption properties of lithium and potassium inoculated NaA zeolite sorbent

Abstract

One of the most promising methods of radioactive waste decontamination, used salt fusion – sorption purification method with the use of lithium and potassium inoculated NaA zeolite sorbent (LiKNaA) is considered. Sorption properties of inoculated LiKNaA sorbent in the course of salt treatment produced as a result of processing by non-aqueous methods of four fuel elements with dense spent fuel elements from BOR-60 reactor from fission products in the static regime under the conditions of the protective chamber have been studied. The high boundary of salt mass fraction trapped by the sorbent as a result of occlusion is determined. An assessment of decontamination index of salt by cesium and cesium radionuclides distribution coefficient in the sorbent is carried out. On the basis of the performed researches, the recommended salt - LiKNaA sorbent mass ratio is proposed at which the salt decontamination index will be not less than 9 and the mass fraction of sodium, lithium, and potassium in the salt varies nonessentially, which allow us to regenerate salt many times for recovery to the process.