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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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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
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.