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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.
Chlng-Kong Chao, Che-Chung Tseng
Nuclear Technology | Volume 101 | Number 2 | February 1993 | Pages 202-211
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34781
Articles are hosted by Taylor and Francis Online.
A loading-rate-dependent model has been developed for the analysis of pellet/cladding mechanical interaction that takes the power ramp rate into account. Based on knowledge of the local strain rate behavior, the effect of ramp rate on fuel rod performance is well described by using the strain energy density criterion. The threshold value of the strain energy density for fuel cladding is determined from the Studsvik Inter-Ramp Project experimental data in conjunction with stress analysis. The critical strain energy density for recrystallized Zircaloy-2 is found to be 0.32 MPa. With this value, the damage zone of cladding for a specific fuel rod design under various burnups, ramp rates, and ramped terminal linear heat generation rates can be established, and the ramp rate effect is well identified.