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RESULTS OF VOLATILITY PILOT PLANT COLD URANIUM FLOWSHEET DEMONSTRATION RUN TU-1

Technical Report ·
DOI:https://doi.org/10.2172/4125421· OSTI ID:4125421
A two-element dissolution of 50.89 kg of Zr-U alloy fuel element with 92 g/min of anhydrous HF in NaF- LiF-ZrF/sub 4/ fused salt at 490 to 670 deg C was made with the fuel element 113% submerged. Initial and final ZrF/sub 4/ contents in the equimolar NaF- LiF fused salt were 25.1 and 40.3 mole%, respectively. Fluorination of the dissolver salt was accomplished with 12 SLM fluorine flow at 500 to 505 deg C. The sorption-desoxption cycle of UF/sub 6/ on NaF was accomplished at 100 and 100 to 400 deg C, respectively, in two fixed-bed absorbers. Product UF/sub 6/ was collected in a cold trap. A complete uranium material balance over the run was not made. However, nonrecoverable uranium losses for the run were only 0.362 g. Product impurity level was <1421 ppmn total cations based on UF/sub 6/ with Na at 1300 ppm being the major impurity. A fuel dissolution rate of 2.52 kg/hr was obtained with an over-all HF utilization of 35.2%. Fluorine utilization was 5.7% for 99.90% conversion of the UF/sub 4/ to UF/sub 6/. Final salt U content was 1.2 ppm. Fluoride salt recovery was 100.5%. The generation of approximates 300 g of off-gas solids occurred during dissolution. (auth)
Research Organization:
Oak Ridge National Lab., Tenn.
DOE Contract Number:
W-7405-ENG-26
NSA Number:
NSA-18-006885
OSTI ID:
4125421
Report Number(s):
ORNL-TM-752
Country of Publication:
United States
Language:
English