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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.
A. L. Ward
Nuclear Technology | Volume 24 | Number 2 | November 1974 | Pages 201-215
Technical Paper | Material | doi.org/10.13182/NT74-A31475
Articles are hosted by Taylor and Francis Online.
An experimental characterization of the effects of thermal treatments and of fast-neutron irradiation on the elevated-temperature tensile and creep-rupture properties of a gas tungsten-arc-deposited Type 316 stainless steel has been completed. Intermediate-temperature (1472°F) stress relief and high-temperature (1950°F) solution an— nealing produce changes in the mechanical properties, some of which may be correlated with coincident changes in the microstructure. Irradiation-induced property changes observed in the weld metal are broadly consistent with trends established for wrought Type 316; however, the extent of property change clearly depends on the condition (heat treatment) of the material as well as fluence, irradiation temperature, and test temperature.