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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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A wave of new U.S.-U.K. deals ahead of Trump’s state visit
President Trump will arrive in the United Kingdom this week for a state visit that promises to include the usual pomp and ceremony alongside the signing of a landmark new agreement on U.S.-U.K. nuclear collaboration.
W. R. Martin, J. R. Weir
Nuclear Technology | Volume 1 | Number 5 | October 1965 | Pages 478-483
Technical Paper | doi.org/10.13182/NT65-A20559
Articles are hosted by Taylor and Francis Online.
The ductility of irradiated structural alloys is of concern in reactor design. The purpose of this study is to determine some of the parameters affecting such ductility. Type-304 stainless steel has been thus investigated up to 600°C. In general, the ductility of stainless steel, solution annealed prior to irradiation, is better than steel cold worked prior to irradiation. One exception to this generality occurs under the conditions of irradiation followed by straining at 200°C, where low ductility is observed for irradiated stainless steel, solution annealed prior to irradiation. Cold working followed by carbide precipitation at an intermediate temperature improves the ductility of irradiated stainless steel at 200°C.