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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.
W. F. Murphy, H. E. Strohm
Nuclear Technology | Volume 4 | Number 4 | April 1968 | Pages 222-229
Technical Paper and Note | doi.org/10.13182/NT68-A26320
Articles are hosted by Taylor and Francis Online.
Segments of Type-304L stainless-steel cladding from irradiated EBR-II fuel elements have been used for burst tests from room temperature to 1000°C. The cladding had accumulated exposures of (0.5 to 1.4) × 1022 n/cm2 (> 0.1 MeV) at temperatures between 370 and 500°C. In burst tests at ≤ 700°C, the greater strength was on the lower half of the irradiated cladding where the irradiation temperature was < 475°C. Tests at 800, 900, and 1000°C each showed uniform strength along the lengths of the cladding. The strength of the irradiated specimens decreased most rapidly with temperatures between 400 and 700°C. Unirradiated specimens were weaker than irradiated ones below 700°C; above 700°C, the unirradiated specimens were slightly stronger. The irradiated and the unirradiated specimens had low uniform strain (∼1 and ∼10%, respectively) at temperature of ∼ 400 to 500°C.