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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
Standards Program
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
Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
D. B. Trauger, J. A. Conlin, Jr.
Nuclear Science and Engineering | Volume 9 | Number 3 | March 1961 | Pages 346-356
Technical Paper | doi.org/10.13182/NSE61-A25886
Articles are hosted by Taylor and Francis Online.
A compact forced-circulation test loop for obtaining corrosion data applicable to molten-salt-fueled reactors has been operated in the MTR (HB-3) beam hole. Several tests were conducted with two fused-salt mixtures, NaF-ZrF4-UF4 and Li7F-BeF2-UF4, in loops constructed, respectively, of Inconel and INOR-8 (nominal composition: 70% Ni, 16% Mo, 7% Cr, 5% Fe, 2% other alloying elements). The maximum loop temperature ranged from 1300 to 1600°F. Engineering aspects of loop design and operation are described.
