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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|Severe Accidents
Wednesday, August 23, 2023|10:45AM–12:25PM EDT|Columbia 9/10
Session Chair:
David L. Luxat
Session Organizer:
Alternate Chair:
Fulvio Mascari
To access paper attachments, you must be logged in and registered for the meeting.
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Sensitivity Analysis of Consequential Steam Generator Tube Rupture (C-SGTR) of Typical Korean NPP
10:45–11:05AM EDT
Byeonghee Lee (KAERI), Jin Ho Song (KAERI), Kwang Soon Ha (KAERI)
Paper
A Methodology for Real-Time Identification of a PWR Accident and Predictive Analysis
11:05–11:25AM EDT
Paul McMinn (Fauske & Assoc.), Nick Karancevic (Fauske & Assoc.), Chan Y. Paik (Fauske & Assoc.), Wei Wei (China Nuclear Power Operation Technology Corp.), Ma Guoyang (China Nuclear Power Operation Technology Corp.)
Presentation Slides (Visible to Attendees)
Hysteresis Impacts in Steady Flow Transitions of the Rayleigh Bénard Problem with Internal Heating; Implications on Heat Transfer Margin in External Reactor Vessel Cooling Strategies
11:25–11:45AM EDT
A. Lentner (George Washington Univ.), E. Balaras (George Washington Univ.)
Source Term Uncertainty Analysis of Severe Accidents in Nordic BWRs
11:45AM–12:05PM EDT
Govatsa Acharya (Royal Institute of Technology), Ioannis Komlikis (Royal Institute of Technology), Dmitry Grishchenko (Royal Institute of Technology), Pavel Kudinov (Royal Institute of Technology), Sergey Galushin (Vysus Group)
