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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
Daniel Cubicciotti, B. C. Syrett, R. L. Jones
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 720-723
Technical Note | Material | doi.org/10.13182/NT81-A32816
Articles are hosted by Taylor and Francis Online.
The effect of surface condition on the initiation of iodine-induced stress corrosion cracks in Zircaloy tubing was investigated. The internal surface of the Zircaloy tubing was given one of three surface treatments, namely etching, grit blasting, or shot blasting. Each of these treatments can readily be performed commercially on Zircaloy fuel cladding. Specimens of surface-treated tubing were locally stressed in an iodine environment at 590 K by indenting the outer surface of the tube wall with a small steel ball. The crack initiation pattern on the inner surface was examined in a scanning electron microscope. Crack initiation was found to be least developed for etched surfaces, was most developed for shot-blasted surfaces, and was developed to an intermediate degree for grit-blasted surfaces. Apparent anomalies between these crack initiation data and the time to failure data obtained previously in tube pressurization tests are rationalized on the basis of the cracking processes.