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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.
J. P. McBride, K. H. McCorkle, Jr., W. L. Pattison, B. C. Finney
Nuclear Technology | Volume 13 | Number 2 | February 1972 | Pages 148-158
Technical Paper | Chemical Processing | doi.org/10.13182/NT72-A31049
Articles are hosted by Taylor and Francis Online.
Urania sol is used for preparing uranium oxide microspheres for nuclear reactor fuels. A new process for producing concentrated, 1 M U or more, crystalline urania sols by solvent extraction has been developed. This process is based on a time-temperature conductivity-controlled extraction of nitric acid from a hydrolyzing U(IV) nitrate-formate solution using an amine-in-hydrocarbon extractant. The sols contain predominantly crystalline urania, and are more resistant to rapid, spontaneous gelation and other variations in properties than earlier sols made by solvent extraction. Also, earlier solvent extraction processes produced dilute (0.2-0.3 M U) sols that required concentration to 1 M before making the spheres. The preparation of a satisfactory sol depends on ensuring crystallization of the urania, minimizing uranium oxidation, and having a stable U(IV) nitrate-formate feed solution. Feed solutions were made by reducing uranyl nitrate-formate solution with platinum-catalyzed hydrogen at atmospheric pressure. The reduction requires vigorous agitation of the solution and continuous electrometric monitoring of the U(IV)/U(VI) redox potential to minimize harmful side reactions. The studies include both laboratory development and an engineering-scale demonstration.