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U.S. Department of Energy
Office of Scientific and Technical Information

IMPROVEMENTS IN OR RELATING TO THE PROCESSING OF NUCLEAR REACTOR FUEL ELEMENTS

Patent ·
OSTI ID:4824697

A process for recovering U from irradiated fuel elements also containing Al and Si is given in which solvent extraction of U is not materially affected by the presence of Si. The process is based on the solubility of Si in acid deficient aluminum nitrate solutions and comprises the steps of dissolving the fuel element in a limited quantity of HNO/sub 3/ such that the resulting solution is acid deficient and extracting uranyl nitrate with an organic solvent. The acid deficiency of the solution preferably is between 0.6 and 2 M. (D.L.C.)

Research Organization:
Originating Research Org. not identified
NSA Number:
NSA-15-032251
OSTI ID:
4824697
Report Number(s):
GB 879041
Country of Publication:
United Kingdom
Language:
English