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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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New report lays out path to U.S. nuclear energy dominance
The new report “How America Can Achieve Nuclear Energy Dominance,” from the Working Group on U.S. Nuclear Energy Dominance, outlines a plan of action for the Trump administration that includes deploying new nuclear reactors, developing domestic supply chains, promoting nuclear exports, reforming regulations, and developing the workforce.
Working group chair Todd Abrajano said, “We welcome the Trump administration’s bold moves to kick-start the U.S. nuclear energy sector, but we recognize that President Trump’s executive orders alone can’t achieve our goals.”
Mohy Sabry, Neveen S. Abed, Ahmed Omar, Moamen G. El-Samrah, Mohamed Y. M. Mohsen
Nuclear Science and Engineering | Volume 198 | Number 10 | October 2024 | Pages 1998-2012
Research Article | doi.org/10.1080/00295639.2023.2284441
Articles are hosted by Taylor and Francis Online.
This study examines the feasibility of utilizing mixed-oxide fuel [(U0.9, rgPu0.1) O2] instead of traditional UO2 in nuclear reactors. The utilization of (U0.9, rgPu0.1) O2 is particularly significant as it represents an effective approach to nuclear fuel recycling by combining reactor-grade plutonium extracted from partially used nuclear fuel and depleted uranium obtained through the enrichment process. The fundamental neutronic characteristics, such as the radial power distribution, were investigated using the MCNPX 2.7 algorithm to identify the specific channel for subsequent thermal-hydraulic (TH) analysis. The TH analysis was conducted using COMSOL-Multiphysics, allowing for the estimation of the fuel rod’s axial and radial temperature profiles, as well as the determination of the departure from the nucleate boiling ratio. Furthermore, the coupling between heat transfer and solid structure (SS) was achieved using the Multiphysics tool in COMSOL-Multiphysics. This coupling facilitated the simulation of key SS parameters, including von Mises stress, volumetric strain, and displacement, while considering the influence of heat transfer. The results demonstrate significant improvements and enhanced safety margins when utilizing (U0.9, rgPu0.1) O2.