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Process for vitrifying liquid radioactive waste

  • US 4,514,329 A
  • Filed: 07/06/1982
  • Issued: 04/30/1985
  • Est. Priority Date: 07/06/1981
  • Status: Expired due to Fees
First Claim
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1. A process for vitrifying liquid radioactive waste, comprising the steps of:

  • dissolving at least one water-soluble vitrifying-facilitating inorganic compound selected from the group consisting of boric acid, aluminum hydroxide, lithium nitrate, lithium carbonate, lithium sulfate, magnesium nitrate, magnesium carbonate, magnesium sulfate, calcium nitrate, calcium carbonate, barium nitrate, aluminum nitrate, zinc nitrate, zinc sulfate, zirconium oxynitrate and a hydrate thereof, into a liquid radioactive waste acidified with nitric acidadding to the resulting solution an alcoholic silica sol obtainable through hydrolysis with an acid of at least about 1 part by weight of alkyl silicate to 1 part by weight of the at least one inorganic compound, based on the weight of the oxide, and allowing the resulting solution mixture to gel at a temperature of from room temperature to 50? C.,calcining the resulting gel by microwave radiation, andheating the resulting calcined product to melt, followed by cooling to obtain a vitrified product.

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