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filingDate 1998-07-30-04:00^^<http://www.w3.org/2001/XMLSchema#date>
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publicationDate 1999-06-28-04:00^^<http://www.w3.org/2001/XMLSchema#date>
publicationNumber JP-2912920-B1
titleOfInvention Pretreatment method for dissolving uranium-plutonium mixed oxide in nitric acid
abstract Abstract: PROBLEM TO BE SOLVED: To improve a dissolution rate and solubility during dissolution of nitric acid in a mixed oxide of uranium and plutonium containing impurities, Reduce insoluble residues. During nitric acid dissolution, as much as possible to prevent the occurrence of the NO X gas. SOLUTION: When dissolving a uranium-plutonium mixed oxide containing impurities in nitric acid, the powder is homogenized and mixed, and then 0.2 to 0.3% by weight of MnO 2 is added or mixed. After adding 0.2 to 0.3% by weight of MnO 2 , homogenizing and mixing, molding using the mixed powder, and sintering in a reducing atmosphere (in a hydrogen atmosphere diluted with an inert gas). Prepare sintered pellets. It is dissolved in nitric acid as it is. Alternatively, the sintered pellet thus prepared is oxidized in air at 300 to 350 ° C. and then dissolved in nitric acid.
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