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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
UM conducts molten salt experiment
For 2,300 hours, the molten salt pump Shaft Seal Test Facility (SSTF) operated at the University of Michigan’s Thermal Hydraulics Laboratory, according to an article from UM. The large-scale experiment was designed to evaluate shaft seal performance in high-temperature pump systems. Fewer than 10 facilities worldwide have successfully operated fluoride or chloride salts for more than 100 hours using over 10 kilograms of material.
Mildred J. Bradley, Leslie M. Ferris
Nuclear Science and Engineering | Volume 8 | Number 5 | November 1960 | Pages 432-436
Technical Paper | doi.org/10.13182/NSE60-A25825
Articles are hosted by Taylor and Francis Online.
A grind-leach method for the recovery of uranium from high-density graphite fuel elements containing greater than 5 weight per cent uranium has been developed on a laboratory scale as a head-end treatment for standard tributyl phosphate solvent extraction processes. With fuel ground to −16 mesh, greater than 99.8% of the uranium can be recovered by leaching twice with boiling 15.8 M nitric acid. Uranium recoveries were lower with less concentrated acid, and with fuel of larger particle size or lower uranium concentration. The grind-leach method is not applicable to fuels containing less than 3% uranium. Leaching −16+30 mesh samples of a fuel containing 1.5% uranium and 7.2% thorium with either boiling 15.8 M nitric acid or 15.8 M nitric acid−0.04 M sodium fluoride, resulted in uranium and thorium recoveries of 90 and 86%, respectively.