URANIUM RECOVERY FROM LAPRE-II FUEL SOLUTION BY TBP EXTRACTION
A feed preparation and solvent extraction flowsheet was developed for the recovery and decontamination of highly enriched uranium from the LAPRE-II reactor fuel solution. The fuel solution, U(IV) in concentrated H/sub 3/PO/sup 4/ ' was dilutad, Fe(NO/sub 3/)/sub 3/ added to complex phosphate and supply salting strength, NaNO/sub 2/ added to oxidize U(IV) to U(VI) so that U may be extracted efficiently with 6% TBP. The flowsheet is designed for operation in noncritically safe equipment. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn. (US)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- NSA Number:
- NSA-14-021566
- OSTI ID:
- 4164971
- Report Number(s):
- CF-60-6-84
- Country of Publication:
- United States
- Language:
- English
Similar Records
Uranium(VI) extraction by TBP in the presence of HDBP
URANIUM PHASE EQUILIBRIA IN THE TBP PROCESS
Recovery of plutonium and americium from chloride salt wastes by solvent extraction
Journal Article
·
Sun Feb 28 23:00:00 EST 1999
· Solvent Extraction and Ion Exchange
·
OSTI ID:343788
URANIUM PHASE EQUILIBRIA IN THE TBP PROCESS
Technical Report
·
Wed Feb 28 23:00:00 EST 1951
·
OSTI ID:4356264
Recovery of plutonium and americium from chloride salt wastes by solvent extraction
Conference
·
Sat Oct 01 00:00:00 EDT 1988
· Sep. Sci. Technol.; (United States)
·
OSTI ID:6019466