RECOVERING URANIUM SUBMARINE REACTOR FUELS
The ORNL fluoride volatility pilot plant was modified to study recovery of uranium trom spent nuclear submarine fuel elements. The Zr-U elements are dissolved in NaFLiF-ZrF/sub 4/ in a hydrofluorinator with anhydrous HF at 650 to 500 deg C. The UF/sub 4/ formed is converted to volatile UF/sub 6/ by reaction with elemental fluorine in a newly designed fluorinator at 500 deg C, purified in a NaF sorption-desorption cycle at 100 to 400 deg C in improved absorbers, and collected in a pair of cold traps. The UF/sub 6/ is liquefied and collected. New auxiliary equipment items required were an HF supply system, an HF neutralizer, a fuel element carrier-charger, a molten salt sampler, and a scrubber for removing traces of HF and F/sub 2/ from cell ventilation air. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- Sponsoring Organization:
- USDOE
- NSA Number:
- NSA-15-017012
- OSTI ID:
- 4024734
- Journal Information:
- Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol., Journal Name: Industrial and Engineering Chemistry (U.S.) Formerly J. Ind. Eng. Chem. Superseded by Chem. Technol. Vol. Vol: 53; ISSN IECHA
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
Similar Records
THE FUSED SALT-FLUORIDE VOLATILITY PROCESS FOR RECOVERING URANIUM
A FUSED SALT-FLUORIDE VOLATILITY PROCESS FOR RECOVERY AND DECONTAMINATION OF URANIUM