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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.
C. W. Hunter, R. L. Fish, J. J. Holmes
Nuclear Technology | Volume 27 | Number 3 | November 1975 | Pages 376-388
Department | Fuel | doi.org/10.13182/NT75-A24311
Articles are hosted by Taylor and Francis Online.
Internally pressurized specimens of unirradiated 20% cold-worked Type 316 stainless-steel cladding were rapidly heated and burst to determine mechanical behavior under various simulated reactor transient events. The tests were conducted at heating rates of 10 and 200 F°/sec. Failure temperatures from 500 to 2500°F were obtained, with the principal emphasis on the behavior above 1000°F. Failure temperatures increased with decreasing internal pressure while cladding ductility initially increased with increasing failure temperature, but above ∼2100°F the ductility decreased steadily with increasing temperature. The increase in ductility with increasing temperature was due to recovery and recrystallization of the cold-worked material, while the decrease above 2100°F resulted from grain growth. The diametral failure strains were between 0.5 to 1.0% at 1000°F. The maximum diametral failure strain values reached 8% for the 10 F°/sec ramp and 4% for the 200 F°/ sec ramp at the elevated temperatures.