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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.
S. Shann, D. R. Olander
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 407-409
Technical Note | Nuclear Fuel Cycle Education Module / Nuclear Fuel | doi.org/10.13182/NT81-A32649
Articles are hosted by Taylor and Francis Online.
A crack-growth model of stress corrosion cracking (SCC) has been successfully applied to predict times-to-failure of Zircaloy specimens exposed to iodine vapor. Data for two types of tests were analyzed using the model The first was a variable loading experiment in which failure occurred after the specimen had been subjected to two distinct stresses in succession. The second was a series of tests in which surface roughness, and probably residual stress as well, was reduced by chemical polishing of the specimens. The success of the crack growth model in dealing with these situations suggests that crack propagation rather than crack initiation is the rate-controlling step in iodine SCC of Zircaloy. Furthermore, the metal in the vicinity of the growing crack is apparently so embrittled by iodine that a model originally intended for ceramics applies.