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Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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Center for Used Fuel Research: Building confidence in storage and transport
Used nuclear fuel storage and transportation have reached a critical juncture.
Dozens of utilities need reliable data on how used nuclear fuel performs in dry storage casks and canisters to extend regulatory licenses at sites across the United States. Likewise, the Department of Energy expects to take ownership of the used nuclear fuel—termed “spent nuclear fuel” in the laws and regulations governing its stewardship—and transfer it to one or more federal staging facilities for management and disposition.
Meanwhile, dozens of reactor companies are testing prototypes of advanced reactors and advanced reactor fuels. Eventually, regulators and industry must also verify the safety and security of storage methods for these advanced fuel types.
To help address these challenges, the DOE established the Center for Used Fuel Research (CUFR) in January 2026 for work related to the long-term storage and transport of used nuclear fuel.
Technical Session|Advanced Reactors
Tuesday, August 18, 2026|1:30–3:15PM CDT|Promenade Ballroom B
Session Chair:
Michael Simpson (University of Utah)
Alternate Chair:
Jinsuo Zhang (Virginia Tech)
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Integrated Off-Gas System for Molten Salt Reactor: A Perspective
1:30–1:50PM CDT
Patricia D. Paviet (PNNL)
Paper
Corrosion Prevention in NaCl-KCl Molten Salt by Heat Treatment of Inconel 625 with Zr Metal
1:50–2:10PM CDT
Kyeongtae Park (Ulsan National Institute of Science and Technology), Jaeyeong Park
Solidification Behavior of Chloride Molten Salt on Powder and Single-Crystal Salt Media
2:10–2:30PM CDT
Junwon Kim (Seoul Nat'l Univ.), Sujeong Lee (Seoul Nat'l Univ.), Taehoon Park (Seoul Nat'l Univ.), Jihwan Kim (Hyundai), Jongwoo Lee (Hyundai), Inwoo Cho (Hyundai), Sungyeol Choi (Seoul Nat'l Univ.)
Comparison of Core Size for MSDR Fuel Salts Up To HALEU Enrichment
2:30–2:50PM CDT
Andrew J. Conant (ORNL), Richard L. Reed (ORNL)
Molten Salt Microreactor Model for Burnup and Consequence Analysis
2:50–3:10PM CDT
Kevin Donnelly (ORNL), Donny Hartanto (ORNL), Manit D. Shah (ORNL)