Abstract

Glass-ceramic is considered as a promising material for processing high-level radioactive waste. In order to treat the waste salt produced after electrolytic refining, the ceramics REPO4, Cs3PO4 and Ba0.6Sr0.4TiO3 were prepared. The analysis results indicated that RE and Cs were fixed in the ceramic lattice of REPO4 and Cs3PO4, and Sr and Ba were fixed in ceramic lattice of Ba0.6Sr0.4TiO3, the Cl− from salt was fixed in the lattice of sodalite. Phosphate ceramics had good heat resistance, and Ba0.6Sr0.4TiO3 a dense tetrahedral structure. These ceramics were jointly embedded in borosilicate and iron phosphate glass, respectively. The maximum embedding rate of mixture of salt containing ceramics and zeolite 4A in the two glass matrices could reach 30 wt.%. To investigated the stability of the two types of glass-ceramics, the leaching rate of each element was measured, which indicated that all elements had good leaching resistance on the 28th day.

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