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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.
T. C. Gillett, R. S. Denning, J. L. Ridihalgh
Nuclear Technology | Volume 31 | Number 2 | November 1976 | Pages 244-249
Technical Paper | Shielding | doi.org/10.13182/NT76-A31686
Articles are hosted by Taylor and Francis Online.
Techniques have been developed for the shield design computations of facilities for the handling and processing of plutonium. These techniques involve the application of a modified version of the point kernel code QAD. Because this modified point kernel code maintains the three-dimensional flexibility and computational efficiency of other point kernel codes, it is well suited to the performance of production shielding-design calculations. Correction factors were developed to account for some inadequacies of the point kernel approach. The accuracy of the code has been determined by comparing results obtained for typical shield configurations with ANISN results and has been found to be adequate for most shielding problems encountered in facilities of this type. Limited comparison to available experimental data indicates the techniques give reasonably good accuracy. Sources of radiation considered include neutrons and gammas from fission, neutrons from (α, n) interactions with light elements, and low-energy gammas from alpha decay.