Vitrification of borate waste generated by nuclear power plants

Berate waste is the main liquid waste generated by nuclear power plants (NP Ps). Vitrification is conceptually attractive because of the potential dura bility of the final product, the flexibility of the process in treating a w ide variety of waste streams, and the economy of barge volume reduction. Th e vitrification of borate waste from NPPs, including the glass formulation and product characterization, is examined. The Minimum Additive Waste Stabi lization (MAWS) concept was utilized to design the glass formulation. The g lass formulation named SL-1, which can incorporate 45 wt% of waste oxides, was selected. The SL-1 glass has good chemical stability, the melting tempe rature is 1000 degrees C, and the viscosity of molten glass is similar to 5 .0 Pa.s at 1000 degrees C. The borosilicate glass form could satisfactorily solidify berate waste with high volume reduction.