FIELD: chemistry.
SUBSTANCE: invention can be used in production of nuclear fuel with the required content of the 235U isotope. Uranium-containing materials with different content of the 235U isotope are mixed in a ratio defined by the equation: where mn is mass of the n-th (unknown) material, g; mi is mass of the i-th material, g; Cn is content of uranium in the n-th material, %; Ci is content of uranium in the i-th material, %; Rn if content of the 235U isotope in the mass of uranium of the n-th material, %; Ri is content of the 235U isotope in the mass of uranium in the i-th material, %; Rgiven is the required (given) content of the 235U isotope in the obtained uranium oxide, %. The obtained uranium-containing material is dissolved in nitric acid and uranium undergoes peroxide precipitation. The precipitate is calcined in air to uranium oxide.
EFFECT: invention simplifies the process of obtaining uranium oxide and increases output.
1 tbl, 6 ex
Title | Year | Author | Number |
---|---|---|---|
PROCEDURE FOR PROCESSING URANIUM-MOLYBDENUM COMPOSITION | 2009 |
|
RU2395857C1 |
METHOD OF PROCESSING URANIUM-CONTAINING COMPOSITIONS | 2008 |
|
RU2379775C1 |
METHOD FOR RECOVERING URANIUM-ALUMINUM WASTE OF NUCLEAR INDUSTRY | 2006 |
|
RU2314582C1 |
PROCESS OF PREPARING METALLIC URANIUM FROM URANIUM PRODUCTION WASTE AND EQUIPMENT | 2002 |
|
RU2236477C2 |
METHOD OF PROCESSING URANIUM-ZIRCON WASTES | 2008 |
|
RU2379776C1 |
METHOD OF PROCESSING URANIUM-CONTAINING COMPOSITION | 2007 |
|
RU2343119C1 |
METHOD OF URANIUM-CONTAINING COMPOSITION PROCESSING | 2009 |
|
RU2396211C1 |
URANIUM EXTRACTION AFFINAGE PROCESS | 2005 |
|
RU2295168C1 |
METHOD OF PROCESSING URANIUM-MOLYBDENUM COMPOSITION | 2012 |
|
RU2502142C1 |
METHOD AND DEVICE FOR PELLETIZING NUCLEAR FUEL FROM URANIUM OXIDE WASTES | 1998 |
|
RU2152087C1 |
Authors
Dates
2011-01-10—Published
2009-07-06—Filed