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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.
Sham Sunder
Nuclear Technology | Volume 122 | Number 2 | May 1998 | Pages 211-221
Technical Paper | Radiation | doi.org/10.13182/NT98-A2863
Articles are hosted by Taylor and Francis Online.
Alpha, beta, and gamma dose rates in water, in contact with the reference used fuel in the Canadian Nuclear Fuel Waste Management Program (i.e., Bruce A CANDU fuel, burnup 685 GJ/kg U), are calculated as a function of cooling time. Procedures to calculate the dose rates for used CANDU fuels of different burnups from results obtained for the reference fuel are described. These procedures can be adapted to estimate dose rates for fuels other than CANDU fuel. The dose rate information is needed to compare the results of leaching and corrosion experiments, conducted by different groups, with used fuels of different burnups and/or cooling times and to predict the effects of radiolysis of groundwater on used fuel oxidation and dissolution in a disposal vault.