Possibility of spent fuel industrial reprocessing on the basis of an uranium-beryllium composition

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GNTs VNII Neorganicheskikh, Materialov, Moscow, Russia ^{[1
]}

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Atomnaya Energiya | 1997年 / 83卷 / 06期

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摘要：

Nuclear fuel reprocessing

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页码：452 / 455

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[21] EMPIRICAL EXPRESSIONS RELATING DEPLETION AND ISOTOPIC COMPOSITION OF SPENT HIGHLY ENRICHED URANIUM FUEL
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[23] Methods of Extracting a Small Quantity of Impurities during Rectification of Uranium Hexafluoride in Fluoride Gas Reprocessing of Spent Nuclear Fuel
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[24] Methods of Extracting a Small Quantity of Impurities during Rectification of Uranium Hexafluoride in Fluoride Gas Reprocessing of Spent Nuclear Fuel
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[25] Mathematical Model of Cadmium Distillation at the Stage of Pyrochemical Reprocessing of Spent Mixed Uranium-Plutonium Nitride Nuclear Fuel
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[26] Purification of Gaseous Emissions by 14C Removal During Reprocessing of Spent Uranium-Plutonium Nuclear Fuel
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[27] Mathematical Model of Cadmium Distillation at the Stage of Pyrochemical Reprocessing of Spent Mixed Uranium-Plutonium Nitride Nuclear Fuel
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[28] Ruthenium Capture from the Gas Phase during Reprocessing of Spent Uranium-Plutonium Nitride Fuel from Fast Reactors
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[30] PROPERTIES AND BEHAVIOR OF THE HIGH-ACTIVITY WASTES FROM THE EXPERIMENTAL GAS-FLUORIDE REPROCESSING OF SPENT URANIUM-PLUTONIUM AND URANIUM FUEL OF THE BOR-60
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