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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.
Prodyot Roy, C. N. Spalaris
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 259-269
Technical Paper | Materials | doi.org/10.13182/NT55-259
Articles are hosted by Taylor and Francis Online.
A development program was undertaken to support the materials selection for steam generator piping and intermediate heat exchangers that are to be used in liquid-metal fast breeder reactors. Four major topics have been reviewed, and the results obtained as well as the direction of future tests have been described. These topics are carbon transport in sodium, the effect of carbon loss/gain on materials in the reactor intermediate heat transport system (IHTS), corrosion fatigue, and aqueous corrosion. Thus far, the results on hand support the initial assumptions made in specifying the use of Cr—1 Mo as the construction material for the evaporator and superheater and Type 316 piping of the IHTS. The future direction of the experimental programs is to verify further the materials choice and also to obtain information that will be essential during the plant installation and operation and the reliability of the components.