NEW LABORATORY DEVELOPMENTS IN THE ZIRCEX PROCESS
A new Zircex flowsheet is proposed in which the nonvolatile products from hydrochlorination of uranium-zirconium alloys are chlorinated with carbon tetrachloride, thereby avoiding the loss of 1 to 6% of the uranium observed in engineering development studies of the older flowsheet for STR fuel in which the hydrochlorination residue was dissolved in nitric acid. Other potential advantages of the new flowsheet include decreased corrosion and elimination of possible explosions between uranium--zirconium alloys and nitric acid. The uranium may be recovered by aqueous dissolution and solvent extraction or by gas- phase fluorination at 200 to 400 deg C of uranium chlorides. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn.
- DOE Contract Number:
- W-7405-ENG-26
- NSA Number:
- NSA-15-019459
- OSTI ID:
- 4000618
- Report Number(s):
- ORNL-2992
- Country of Publication:
- United States
- Language:
- English
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