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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.
L. R. Pederson, C. Q. Buckwalter, G. L. McVay
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 151-158
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT83-A33214
Articles are hosted by Taylor and Francis Online.
Silicon solubility limitations appear to control the rate of corrosion of a complex simulated nuclear waste glass at relatively high values of the glass surface area to solution volume ratio (SA/V). Undersaturated glass components such as sodium and boron were affected by SA/V in a manner similar to silicon. Under relatively low SA/V conditions, glass corrosion was unaffected by changes in the SA/V ratio. Congruent dissolution was never observed, in contrast to previous results for simple and certain complex silicate glasses. Increases in the SA/V value may be a viable method for performing accelerated leach resistance testing of nuclear waste forms.