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Conference Spotlight
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
M. A. Shinaishin, M. A. Abolfadl, A. S. Khedr, M. M. Kamel
Nuclear Science and Engineering | Volume 136 | Number 3 | November 2000 | Pages 376-387
Technical Paper | doi.org/10.13182/NSE00-A2166
Articles are hosted by Taylor and Francis Online.
This work aims at simulating steam Zircaloy clad interaction in a wide range of temperatures extending to those expected in severe accident conditions of nuclear power plant light water reactors. The equations governing interaction variables for a two-layer (-oxide) and three-layer (--oxide) structure are analytically solved for a semi-infinite and for a finite metal thickness. This method has great computational advantages (small calculation time with no divergence problem) compared with the numerical solution methods, and it can be accurately applied at high temperatures and for finite metal thickness compared to published parabolic correlations, which yield large deviations from experimental data at these conditions. Variables such as oxidation rates, steam consumption, hydrogen generation, and heat released due to oxidation are very important in identifying reactor core degradation scenarios. We thus focused on predicting them as accurately as possible. The predicted oxidation rates at constant temperatures and under constant heating rates are compared with available experimental data for Zircaloy-4, and good agreements were observed. The results reflect the importance of the oxidation heat generation as a heat source in severe accidents knowing that the reactor core contains large quantities of structural metals.