| 摘要 |
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 |
