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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.
R. C. Lloyd, E. D. Clayton, J. H. Chalmers
Nuclear Technology | Volume 4 | Number 3 | March 1968 | Pages 136-141
Technical Paper and Note | doi.org/10.13182/NT68-A26376
Articles are hosted by Taylor and Francis Online.
The results of neutron multiplication measurements performed with arrays of 233U solution apply to criticality safety considerations in handling solutions at a concentration of ≈ 330 g 233U/liter and are useful in checking computational methods. The measurements were made with ≤ 17.3 kg 233U in both reflected and unreflected arrays. Critical numbers of bottles were determined as a function of spacing, and the effect of adding moderating material between the bottles comprising an array was also examined. Monte Carlo calculations were found to reproduce the experimental data reasonably well, with keff being computed to within about 0.03 of unity for those cases compared.