Method of disposal of liquid, sodium and boron containing radioactive wastes from nuclear power plants

A new method of the disposal of liquid radioactive wastes with a high sodium and boron content consists in their vitrification in phosphate glass. Cementation, bituminization, polymerization and vitrification are described and their disadvantages listed. According to the proposed procedure, phosphorus or its oxygen compound are added to the radioactive waste solution. The final concentration of phosphoric oxide in the final product of solidification is within 20 - 70 wt.%. Compounds of aluminium and/or iron and/or zinc and/or calcium and/or lead are then added. The final concentration of their oxides in the resulting product does not exceed 30 wt.%. The resulting solution or suspension is heat-processed to the sintering or melting temperature in the range of 400 - 1200 degC. The product of solidification is a substance of glass, crystalline or glass-crystalline character. Its resistance to water and melting temperature depend on the content of the individual components. (Pu)