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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.
T. J. Hurley, Jr., H. R. Fike, and G. F. O'Neill
Nuclear Science and Engineering | Volume 12 | Number 3 | March 1962 | Pages 341-347
Technical Paper | doi.org/10.13182/NSE62-A28084
Articles are hosted by Taylor and Francis Online.
Studies performed in the Process Development Pile of the Savannah River Laboratory have provided precise measurements of the material bucklings of a number of D2O-moderated lattices of natural uranium metal rods over an extended range of fuel assembly sizes and lattice pitches. The 1-in. uranium rods were clad with 0.032 in. of aluminum. Fuel assembly sizes varied from single rods to clusters of 3, 7, and 19 rods (0.09 to 1.81 kg U/cm) and lattice spacings from 7.00 to 21.00 in., covering a range of moderator-to-fuel volume ratios from 10.23 to 161.53. A few lattices were studied at different D2O purities, in loadings of different sizes, and in reflected loadings.
