FIELD: the invention refers to the field of treatment with spent nuclear fuel.
SUBSTANCE: the mode of processing irradiated nuclear fuel is in thermal oxidation of uranium dioxide on air and regeneration of received uranium protoxide in surroundings of hydrogen contents. At that oxidation-regeneration stages are conducted repeatedly. The oxidation is carried on at temperature 700-800°C and regeneration- at temperature 600-700°C. After that annealing of uranium dioxide is conducted at temperature 1000-1300°C with simultaneous vacuum distillation of volatile products of fission particular of caesium.
EFFECT: the advantages of the invention is in effective withdrawal of products of fission and in the reduction of the activity of fuel.
4 cl,1 dwg, 1 ex
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Authors
Dates
2005-06-10—Published
2004-06-28—Filed