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Conference Spotlight
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.
D. Kedem, M. Lemanska
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 152-158
Technical Paper | Fuels for Pulsed Reactor / Radioisotope | doi.org/10.13182/NT76-A31548
Articles are hosted by Taylor and Francis Online.
The thermal-neutron flux produced by a 252Cf spontaneous fission neutron source was computed for various spherical assemblies with moderators of iron, aluminum, carbon, D2O, beryllium, and H2O and reflectors of H2O and carbon. Consideration of spherical assemblies with a 252Cf source located at the center and at various distances from the center lead to a configuration, adaptable to neutron radiography, that has a small thermalization factor and a flat thermal-neutron flux.
