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US5264159A Process for treating salt waste generated in dry reprocessing of spent metallic nuclear fuel 失效
用于处理废金属核燃料的干后处理中产生的盐废物的方法

Process for treating salt waste generated in dry reprocessing of spent
metallic nuclear fuel
摘要:
A salt waste composed mainly of chlorides, which is generated from the step of a molten salt electrolytic purification in dry reprocessing of a spent metallic nuclear fuel, is reacted with boric acid at high temperature to convert the chlorides in the salt waste into oxides. The resulting oxides of the salt waste are easily vitrifiable, and a vitrification product is obtained by adding a vitrifying additive to the oxides, heat-melting the mixture to form a molten mixture and cooling the molten mixture.
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