Patent Number: 051851040
Section: claims

1. A method of treatment of a high-level radioactive waste of a nitric acid solution obtained as an extraction residue in reprocessing of spent nuclear fuels, said method consisting essentially of: calcining the nitric acid solution to evaporate moisture and nitric acid in the solution to thereby obtain a calcined radioactive waste;  heating the calcined radioactive waste to a temperature ranging from about 500.degree. to about 3,000.degree. C. to vaporize a portion of the elements contained in the radioactive waste, the respective elements being vaporized in the form of metal or oxide thereof; and  obtaining as a residue, a volume-reduced high-level radioactive solid.  calcining the nitric acid solution to evaporate moisture and nitric acid in the solution to thereby obtain a calcined radioactive waste;  heating the calcined radioactive waste in the presence of a reducing agent at a temperature ranging from about 500.degree. to about 3,000.degree. C. to vaporize a portion of the elements contained in the radioactive waste, the respective elements being vaporized in the form of metal; and  obtaining as a residue, a volume-reduced high-level radioactive solid.  calcining the nitric acid solution to evaporate moisture and nitric acid in the solution to thereby obtain a calcined radioactive waste;  heating the calcined radioactive waste to a temperature ranging from about 500.degree. to about 3,000.degree. C. to vaporize a first portion of the elements contained in the radioactive waste, the respective elements being vaporized in the form of metal or oxide thereof;  heating the remaining radioactive waste in the presence of a reducing agent at a temperature ranging from about 500.degree. to about 3,000.degree. C. to vaporize a second portion of the elements contained in the remaining radioactive waste, the respective elements being vaporized in the form of metal; and  obtaining as a residue, a volume-reduced high-level radioactive solid.  calcining the nitric acid solution to evaporate moisture and nitric acid in the solution to thereby obtain a calcined radioactive waste;  heating the calcined radioactive waste in the presence of a reducing agent at a temperature ranging from about 500.degree. to about 3,000.degree. C. to vaporize a portion of the elements contained in the radioactive waste, the respective elements being vaporized in the form of metal and including cesium, strontium or cesium and strontium; and  obtaining as a residue, a volume-reduced high-level radioactive solid containing therein no cesium and strontium. 2. The method according to claim 1, which further comprises cooling stepwise the resultant vapor at different temperatures each corresponding to the sublimation or boiling point of each metal or each oxide thereof to separately collect the respective elements. 3. A method of treatment of a high-level radioactive waste of a nitric acid solution obtained as an extraction residue in reprocessing of spent nuclear fuels, said method consisting essentially of: 4. The method according to claim 3, which further comprises cooling stepwise the resultant vapor at different temperatures each corresponding to the sublimation or boiling point of each metal to separately collect the respective elements. 5. A method of treatment of a high-level radioactive waste of a nitric acid solution obtained as an extraction residue in reprocessing of spent nuclear fuels, said method consisting essentially of: 6. The method according to claim 5, which further comprises cooling stepwise the resultant vapor of the first portion of the elements at different temperatures each corresponding to the sublimation or oiling point of each metal or each oxide thereof to separately collect the first portion of the elements, and cooling stepwise the resultant vapor of the second portion of the elements at different temperatures each corresponding to the sublimation or boiling point of each metal to separately collect the second portion of the elements. 7. A method of treatment of a high-level radioactive waste of a nitric acid solution obtained as an extraction residue in reprocessing of spent nuclear fuels and containing cesium, strontium or cesium and strontium, said method consisting essentially of: