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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.
F. N. Mazandarany, P. L. Rittenhouse
Nuclear Technology | Volume 28 | Number 3 | March 1976 | Pages 406-423
Technical Paper | Reactor | doi.org/10.13182/NT76-A31523
Articles are hosted by Taylor and Francis Online.
The literature pertinent to the steam and water corrosion of high-temperature gas-cooled reactor (HTGR) steam generator materials was reviewed and used to corroborate the expected excellent performance of Incoloy 800 and 2¼ Cr—1 Mo steel. Similarly, available information on HTGR primary coolant-metal compatibility (helium corrosion) was assessed in relation to results obtained in ongoing programs. Quantitative results from these programs were interpreted in terms of a qualitative mechanistic model.