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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.
P. Hurst, H. C. Cowen
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 449-459
Technical Paper | Materials | doi.org/10.13182/NT55-449
Articles are hosted by Taylor and Francis Online.
Stress corrosion studies in caustic environments have been carried out on the ferritic 2 1/4 Cr—Mo steel, with particular reference to its use in the evaporators of the U.K. prototype fast reactor. The quench-hard-ened steel has been found to be susceptible to stress corrosion cracking (SCC) throughout the temperature range of 50 to 300°C. In 30% caustic soda at 116°C, this susceptibility extends over the potential range −900 to +100 mV (Hg/HgO). On tempering, SCC occurs at −900 to −700 mV, but only at more positive potentials when preceded by an overheating treatment. Mechanisms by which cracking occurs under the different conditions studied are discussed. Cracking can occur in hard tube-to-tube-plate welds exposed to caustic environments as a consequence of fabrication stresses, but it has been shown that this can be avoided by shot-peening.