Patent · US Expired

Process for the batch fine purification of uranium or plutonium recovered in a reprocessing process for irradiated nuclear fuel and/or fertile materials

US4759878A · kind A · utility

8Cited by
6References
42Claims
0Family size

Assignee

Inventors

Key dates

Filing dateMar 5, 1985
Grant dateJul 26, 1988
Priority date
Expiry dateMar 5, 2005

Classification

  • Technology area (CPC Y)Emerging Cross-Sectional Technologies
  • CPC primaryY02W30/50
  • WIPO fieldEngines, pumps, turbines
  • WIPO sectorMechanical engineering

Abstract

Process for the batch purification of uranium recovered in a reprocessing process, after a first separation of impurities, in which for each batch an aqueous, nitric acid uranyl-nitrate solution (UNH original solution), which still contains residual amounts of impurities, is cooled to crystallize out purified UO.sub.2 (NO.sub.3).sub.2 .multidot.6H.sub.2 O (UNH) from the solution and the resulting crystals are separated out of their mother liquor and washed. The original solution is adjusted to a specified uranium concentration and the adjusted solution is cooled to below 0.degree. C. to bring about the crystallization. The duration between starting and ending the crystallization is held between 0.1 and 10 hours. The amount of the UNH crystals which is crystallized out corresponds to at least about 80 weight % of the uranium content introduced. The ratio of the volume of the crystals formed to the volume of the remaining mother liquor is not larger than 0.5. A final concentration of nitric acid is estabilished in the mother liquor between 6 and 12 mol/l HNO.sub.3 at room temperature. A joint crystallizing out of UNH with water as ice and/or with nitric acid trihydrate (HNO.sub.3 .mu…

Source: USPTO / EPO open patent data. Objective bibliographic and citation counts.