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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.
L. C. Walters, C. M. Walter
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 134-148
Technical Paper | Material | doi.org/10.13182/NT79-A32386
Articles are hosted by Taylor and Francis Online.
Irradiation-induced creep and swelling of stain-less-steel Experimental Breeder Reactor II (EBR-II) components have been the subjects of intense surveillance programs during the operation of the EBR-II. Dilation, length change, and bow due to creep and swelling of stainless-steel ducts have all been of concern during the operation of the EBR-II, but in no instance have significant reliability or safety problems arisen due to these phenomena. Driver-fuel elements of two different designs have been irradiated to cladding breach. It was demonstrated that metal driver fuel is capable of high burnup when designed for interconnected porosity prior to fuel-cladding contact. Cladding breaches were found either adjacent to the fuel column or in the fuel-restrainer dimpler. The breach mode was intergranular cracking at both locations.