A glass formulation for vitrifying of high level liquid radioactive waste and its performance

The borosilicate matrix from ternary system to multi-component system and waste oxides incorporated with matrices are introduced. For the incorporation of waste oxides with and without sulphate, the formulation of No.704 is selected among various formulations, and it can obtain (20 ∼ 30) wt% of incorporating capacity. During the studying of incorporation for high level liquid radioactive wastes contained with SO42-, three kinds of borosilicate matrix are adopted. The analysis shows that the content of SO3 in vitrified glass is (0.3 ∼ 0.6) wt%. As to the added SO42-, some of that is incorporated into vitrified glass and volatilized to the off gas, and the remainder will present as yellow phase on the glass surface. The radioactive elements are enriched in yellow phase material which would seriously affect the quality of vitrified glass. In the test results, the No.704 vitrified glass has the best performance and it will be used as engineering test material for the pot type vitrified project