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Vitrification of Borate Waste Generated by Nuclear Power Plants

Jiawei Sheng, Shanggeng Luo, Baolong Tang

Nuclear Technology / Volume 125 / Number 1 / Pages 85-92

January 1999


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Borate waste is the main liquid waste generated by nuclear power plants (NPPs). Vitrification is conceptually attractive because of the potential durability of the final product, the flexibility of the process in treating a wide variety of waste streams, and the economy of large volume reduction. The vitrification of borate waste from NPPs, including the glass formulation and product characterization, is examined. The Minimum Additive Waste Stabilization (MAWS) concept was utilized to design the glass formulation. The glass formulation named SL-1, which can incorporate 45 wt% of waste oxides, was selected. The SL-1 glass has good chemical stability, the melting temperature is 1000°C, and the viscosity of molten glass is ~5.0 Pas at 1000°C. The borosilicate glass form could satisfactorily solidify borate waste with high volume reduction.

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