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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
E. R. Siegmann, J. C. Gilbertson
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 452-459
Technical Paper | Fuel | doi.org/10.13182/NT75-A24445
Articles are hosted by Taylor and Francis Online.
The consequences of the loss of bond in a sodium-bonded pin were considered. Experiments and previous analyses were reviewed. New calculations were performed and indicated that loss of bond could lead to fuel redistribution within the clad but not to clad failure. Fuel-coolant interactions with carbide fuel were also considered. Interface temperatures between molten fuel and sodium were determined and applied to the Fauske criterion for spontaneous nucleation. Results indicate that rapid sodium vaporization is not likely with carbide fuel. Upper limit work-energy yields were calculated for sodium contact with molten oxide and carbide fuels using SOCOOL-II code. Temperatures, properties, and geometry were varied to determine the relative dependency of the results. The yields were very similar for the carbide and oxide and varied more with the boundary conditions than with the type of fuel.