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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.
P. Shahinian
Nuclear Technology | Volume 38 | Number 3 | May 1978 | Pages 415-426
Technical Paper | Material | doi.org/10.13182/NT78-A32039
Articles are hosted by Taylor and Francis Online.
Fatigue and creep crack propagation in 20 and 25% cold-worked Type 304 and 20% cold-worked Type 316 stainless steels were examined at 427 to 593°C (800 to 1100°F). The resistance to fatigue crack growth was slightly better for Type 304 stainless steel compared to Type 316 stainless steel, and was improved by an increase in cold work; however, these differences were small Compared to solution-annealed stainless steel, the cold-worked steels had higher crack growth resistance at high stress intensity levels. Creep crack growth occurred at 482°C (900°F), but much higher stress intensities, K, were required than in fatigue. However, at 593°C creep and fatigue crack growth occurred over the same K range and, in fact, at higher K levels crack growth in creep was faster than in fatigue. Retardation of crack growth was observed when the load on a specimen was changed from cyclic to static.