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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.
Advances in Thermal Hydraulics (ATH 2024)
Technical Session
Wednesday, November 20, 2024|10:00–11:45AM EST|Coral A
Session Chair:
Rui Hu (ANL)
Alternate Chair:
Bart Verdonschot (NRG)
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A Numerical Test Bed on Algorithms Efficient for Advanced System Analysis Code Development
10:00–10:20AM EST
Ling Zou (ANL), Rui Hu (ANL)
Paper
Implementing a Corrosion-Oxidation Modeling Capability in SAM for Lead-Cooled Fast Reactors
10:20–10:40AM EST
Travis Mui (ANL), Thanh Hua (ANL), Ling Zou (ANL), Rui Hu (ANL), Jun Liao (Westinghouse Electric Co.)
Severe Accident Analysis of OPR-1000 Plant Using CINEMA Code
10:40–11:00AM EST
Jun-young Kang (KAERI), Donggun Son (KAERI), Jae Hyun Ham (KAERI), Yong Mann Song (KAERI), Jun Ho Bae (KAERI)
A New One-Dimensional Model for Thermal Mixing and Stratification in Reactor Applications
11:00–11:20AM EST
Eric Cervi (ANL), Ling Zou (ANL), Yeongshin Jeong (ANL), Rui Hu (ANL)
Development of A System Analysis Model to Evaluate the Conceptual Design of the Reactor Cavity Cooling System of the Horizontal Compact High Temperature Gas-Cooled Reactor (HC-HTGR)
11:20–11:40AM EST
Yeongshin Jeong (ANL), Darius Lisowski (ANL), Qiuping Lv (ANL), Rui Hu (ANL)