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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Latest News
Atomic Canyon partners with INL on AI benchmarks
As interest and investment grows around AI applications in nuclear power plants, there remains a gap in standardized benchmarks that can quantitatively compare and measure the quality and reliability of new products.
Nuclear-tailored AI developer Atomic Canyon is moving to fill that gap by entering into a new strategic partnership with Idaho National Laboratory to develop and release the “first comprehensive benchmark suite for evaluating retrieval-augmented generation (RAG) and large language models (LLMs) in nuclear applications.”
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.