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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.
M. Kaminsky, S. K. Das, R. Ekern
Nuclear Technology | Volume 29 | Number 3 | June 1976 | Pages 303-308
Technical Paper | Fusion Reactor Material / Material | doi.org/10.13182/NT76-A31594
Articles are hosted by Taylor and Francis Online.
The surface damage of insulating ceramic coatings on Hastelloy X and Nb—1% Zr held at room temperature and at 300°C has been studied for both 100- and 250-keV helium ion irradiation for a dose range from 3.7 × 1018 to 1 × 1019 ions cm−2. Blisters were observed after room temperature irradiation with both 100- and 250-keV helium ions. However, for irradiation at 300°C no blisters could be observed. The sharp rise in the helium permeation with temperature, observed by others for some glasses and ceramics, is thought to be responsible for this behavior. These results suggest that for the energy range studied, helium blistering has a negligible surface erosion effect on such coatings if they are operated at temperatures above 300°C.