FIELD: chemistry.
SUBSTANCE: method for nuclear production waste processing involves electrochemical dissolution of fuel rods in a nitric acid solution in an electrolyzer, while maintaining a constant concentration of nitric acid in the range 5.0÷6.0 M. The electrolyzer body is a cathode. The anode is made in the form of a clamp with a possibility of its periodic decompression and compression when the current deviates from the nominal value to 10%. At that, the ratio of the areas of the anode part surface immersed in the solution and the soluble fuel elements is (2÷7):1, and the ratio of current densities at the anode and soluble fuel elements is 1:(2÷7). After electrochemical dissolution, accompanied by shell removal and partial dissolution of uranium, clarified solutions are sent to uranium extraction, and undissolved residues are placed in a mixture of nitric and hydrofluoric acids with addition to aluminum solution at a molar ratio of HF:HNO components3: Al=1:(4÷8):(0.2÷0.4). Clarified solutions are subjected to uranium extraction.
EFFECT: invention allows to increase the uranium recovery during the processing of fuel rods in a stainless-steel shell with a fuel core containing zirconium.
2 cl, 1 tbl
Title | Year | Author | Number |
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METHOD FOR RECYCLING OF NUCLEAR PRODUCTION WASTES | 2008 |
|
RU2370837C1 |
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METHOD OF PROCESSING NUCLEAR WASTES | 2008 |
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METHOD OF PROCESSING URANIUM-ZIRCONIUM WASTES | 2016 |
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RU2613352C1 |
METHOD OF PROCESSING HIGHLY ENRICHED URANIUM | 1998 |
|
RU2131476C1 |
METHOD OF PROCESSING FUEL ELEMENTS | 2018 |
|
RU2707562C1 |
METHOD OF DISSOLVING PLUTONIUM DIOXIDE, MOX-FUEL SCRAP AND EXTRACTING AMERICIUM | 2020 |
|
RU2732081C1 |
Authors
Dates
2018-03-06—Published
2017-04-12—Filed