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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
Standards Program
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.
E. G. Brush
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 246-251
Technical Paper | doi.org/10.13182/NT65-A20509
Articles are hosted by Taylor and Francis Online.
Fuel cladding materials have been corrosion tested under heat-transfer conditions to superheated steam. Each datum point obtained represented an integrated corrosion response over a temperature gradient along the length of an electrically heated test specimen. An analytical model is developed by which these data may be treated to yield corrosion behavior at a given specific temperature. Corrosion rate laws in superheated steam are examined, and particular emphasis is given to the transition from nonlinear to linear rate control. It is argued, in the case of Incoloy-800®, that the transition results in true steady-state linear control, thus allowing the model to be used to extrapolate the corrosion behavior of this alloy to long periods of time.