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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.
R. B. Gordon
Nuclear Science and Engineering | Volume 3 | Number 3 | March 1958 | Pages 232-249
Technical Paper | doi.org/10.13182/NSE58-A25464
Articles are hosted by Taylor and Francis Online.
To achieve adequate corrosion resistance in high-temperature water, the chemical composition and fabrication of zirconium cladding material must be carefully controlled. Present technology permits the satisfactory fabrication of a variety of fuel materials which are compatible with zirconium cladding. Homogeneity and melting crucible problems still exist with some of the fuel alloys. Zirconium-clad fuel elements of the bonded type are produced by pack rolling or coextrusion of the fuel and cladding. The optimum working temperature represents a balance between the need for minimizing differences in plasticity between fuel and cladding and for adequate diffusion at the clad-fuel interface. Unbonded fuel elements require close dimensional control of fuel and cladding and high-quality closure welds which are made possible by the excellent welding characteristics of Zircaloy.