FIELD: production of reconditioned nuclear fuel from rejected pellets and nuclear fuel wastes. SUBSTANCE: nuclear fuel wastes, ground powder, scrape oxides, and ash are subjected to thermal oxidation in the open prior to aqueous cleaning to obtain U3O8oxide; pellets rejected in the process and oxides of nuclear fuel wastes are weighed out, total content of uranium and mass proportion of U235 in mixture of uranium isotopes are determined, calculations are made of amount of U3O8 with high proportion of U235 in uranium isotope mixture to be added to U3O8 oxide so as to produce mixture with rated mass proportion of U235 in uranium isotope mixture using formula for two contents of mass proportions of U235, Device implementing this method is provided with two units for thermal oxidizing in the open to obtain U3O8 oxide of nuclear fuel wastes, two weighing units with U3O8 oxide batcher of which one has high mass proportion of U235 in uranium isotope mixture and other one, low mass proportion of U235 in uranium isotope mixture, unit for dry mixing of U3O8 oxides having high and low mass proportions of U235 in uranium isotope mixture, wet correction unit with batchers of uranyl nitrate having high and low mass proportions of U235 in uranium isotope mixture; all units are arranged in tandem and provided with facilities for conveying wastes being recovered and their half-finished products from one unit to other. EFFECT: improved yield of recovered products. 7 cl, 1 dwg
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Authors
Dates
2000-06-27—Published
1998-11-25—Filed