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Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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Study mapping U-10Zr porosity informs metallic fuel design
Researchers at Idaho National Laboratory and the Massachusetts Institute of Technology have conducted a three-dimensional study of irradiated U-10Zr—uranium alloyed with 10 percent zirconium—across key radial regions, providing new insights into how the material swells, transfers heat, and interacts with the fuel cladding.
U-10Zr was extensively tested in historical sodium-cooled fast reactors and is now attracting attention for use in next-generation advanced reactors.
Technical Session|Experimental Thermal Hydraulics
Wednesday, August 23, 2023|10:45AM–12:25PM EDT|Cardozo
Session Chair:
Guanyu Su (UCB)
Session Organizer:
Bao-Wen Yang (DEDQ)
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Experimental Investigations of Material-Conjugated Subcooled Flow Boiling
10:45–11:05AM EDT
Mingfu He (Univ. New Mexico), Minghui Chen (Univ. New Mexico)
Paper
The Effect of Time Varying Axial Power Shape on Transient Critical Power Performance of BWR Fuel
11:05–11:25AM EDT
B. Ward (Global Nuclear Fuel Americas), S. Oh (Global Nuclear Fuel Americas), J. Andersen (Global Nuclear Fuel Americas), C. Heck (Global Nuclear Fuel Americas), D. Rock (Global Nuclear Fuel Americas), M. Sugawara (Global Nuclear Fuel Americas), J. Lamy (Global Nuclear Fuel Americas)
Presentation Slides (Visible to Attendees)
Steady-State and Power Transient Critical Heat Flux Experiments of FeCrAl and Zircaloy Claddings Under Saturated Pool Boiling
11:25–11:45AM EDT
Experimental Research About Corrosion Effect on Boiling Heat Transfer Performance of Plate-Type Samples with Micro-Structures
11:45AM–12:05PM EDT
Wei Xu (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.), Kun Ouyang (Shanghai Jiao Tong Univ.), Xiaoqiang He (Nuclear Power Institute of China)
Presentation Video (Visible to Attendees) — Wei Xu