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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
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.