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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|Water-Cooled Reactor Operations and Accident Analysis
Thursday, August 24, 2023|9:00–10:20AM EDT|Embassy
Session Chair:
Kyoung-Ho Kang (KAERI)
Alternate Chair:
Cesare Frepoli
Session Organizer:
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Analysis of CRDM Nozzle Rupture LOCA with Loss of Safety Injection at the ATLAS Experimental Facility Using the MARS-KS and TRACE Code
9:00–9:20AM EDT
Hyunjoon Jeong (Incheon Nat'l Univ.), Taewan Kim (Incheon Nat'l Univ.)
Paper
Good Practices for Analyses of Design Extension Condition Without Significant Fuel Degradation for Operating Nuclear Power Plants
9:20–9:40AM EDT
J. Zhang (Tractebel ENGIE), M. Havet (Tractebel ENGIE), A. Bousbia Salah (Bel V), P. Kral (UJV Rez), J. Krhounkova (UJV Rez), A. Guba (Centre for Energy Research), A. Bersano (ENEA), M. Cherubini (NINE), T. Nemec (SNSA), M. Sánchez (CSN), R. Mendizábal (CSN), M. Adorni (OECD NEA), M. Bales (OECD NEA)
Presentation Slides (Visible to Attendees)
Sensitivity Analysis of Transient Critical Heat Flux Phenomena Within RELAP5-3D in the Transient Reactor Test Loop
9:40–10:00AM EDT
Nicholas A. Meehan (Univ. Tennessee, Knoxville), Nicholas R. Brown (Univ. Tennessee, Knoxville)
Comparative Analysis of Passive Safety Feature of G-III+ BWR and PWR
10:00–10:20AM EDT
Xueyan Zhang (Huazhong Univ. Science and Technology), Ye Yang (Huazhong Univ. Science and Technology), Jun Yang (Huazhong Univ. Science and Technology)
Presentation Video (Visible to Attendees)
