Patent · US Expired

Co-solidification of low-level radioactive wet wastes produced from BWR nuclear power plants

US6436025B1 · kind B1 · utility

1Cited by
3References
6Claims
0Family size

Assignee

Inventors

Key dates

Filing dateMar 21, 2000
Grant dateAug 20, 2002
Priority date
Expiry dateMar 21, 2020

Classification

  • Technology area (CPC Y)Emerging Cross-Sectional Technologies
  • CPC primaryY02W30/91
  • WIPO fieldMaterials, metallurgy
  • WIPO sectorChemistry

Abstract

This invention discloses a method for the co-solidification of low-level radioactive wet wastes of BWR nuclear power plants, including concentrate waste, spent ion exchange resins and sludge wastes etc., with very high volume efficiency. In this invention, for promoting the stability of the solidified waste, sodium sulfate in the concentrate solution is converted to sodium hydroxide and barium sulfate by reacting with barium hydroxide. The conversion product barium sulfate possessing high density and stability is insoluble and used as a fine aggregate material in the solidified waste. Sodium hydroxide is used to stabilize ion exchange resins and to form a highly water-durable solidified waste form with silicates and phosphates in the solidification agent mixture. The solidification agent used in this invention is a formulated powder mixture completely made from inorganic materials. Therefore, there is no aging problem of the solidified waste. In this invention, the waste loading of the solidified waste is highly increased due to the conversion of sodium sulfate and the co-solidification of wastes. Thus, the solidification volume efficiency of the present invention is about three ti…

Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.