| 摘要 |
<p>PROBLEM TO BE SOLVED: To mix phosphate in salt waste of a spent molten salt generated from electrolysis purification process of the molten salt during reprocessing a spent fuel in a reactor power station by using the molten salt and solidify to glass with high nuclear species containment and high volume reduction performance. SOLUTION: In an oxide converted from salt waste generated in a metal dry reprocessing method or an oxide converted from excess salt waste generated in an oxide dry reprocessing method, a phosphate is mixed and a vitrifying material is added to it to solidify to glass with high nuclear species containment and high volume reduction performance in this solidification processing method of radioactive waste. The quantity of boric acid added to molten salt waste including volatile salt to convert to an oxide is made 12 to 30 times of stoichiometrically necessary quantity against the volatile salt. The reaction temperature of the molten salt waste and boric acid is set in 800 to 1200 deg.C. The hydrogen chloride generated in the reaction between the molten salt waste and boric acid is made react to an alkali metal. The salt produced by this is reused as the molten salt.</p> |
