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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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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.
V. F. Baston, J. H. McFadden, W. A. Yuill
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 247-256
Technical Paper | Fuel | doi.org/10.13182/NT72-A31114
Articles are hosted by Taylor and Francis Online.
An analytical method based on the steady-state release model developed by Idaho Nuclear Corporation (now Aerojet Nuclear Company) is presented for calculating noble gas and iodine release to the fuel cladding gap of fuel pins in a nuclear reactor operating at steady-state conditions. This method, which employs fission gas capsule data and conservative assumptions (assumptions that result in prediction of maximum release), can be used in reactor safety analysis to predict the fission gases that could be available for release in the event of cladding failure and the pressure exerted by the fission gases on the inside of the cladding during reactor operation.