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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
Wednesday, May 10, 2023|3:45–5:25PM MDT|Idaho Falls Room
Session Chair:
Robert C. O'Brien
Session Organizer:
Alternate Chair:
Michael G. Houts
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The Effects of Hot Hydrogen Exposure on (U,Zr)C Fuel for Nuclear Thermal Propulsion
3:45–4:05PM MDT
Jhonathan Rosales (NASA Marshall Space Flight Center), Arne Croell (Univ. Alabama, Hunstville), Jamelle K.P. Williams (NASA Marshall Space Flight Center), Brian Taylor (NASA Marshall Space Flight Center), Martin Volz (NASA Marshall Space Flight Center), Jason Reynolds (Univ. South Carolina), Christopher McKinney (NASA Marshall Space Flight Center)
Paper
Mechanical Properties and Failure Mechanisms of Cermet Fuel for Nuclear Thermal Propulsion (NTP)
4:05–4:25PM MDT
James Mudd (LANL), Jeremy Watts (Missouri Univ. Science and Technology), Jhonathan Rosales (NASA Marshall Space Flight Center), Ryan Wilkerson (LANL), Brian Taylor (NASA Marshall Space Flight Center), William Fahrenholtz (Missouri Univ. Science and Technology), Gregory Hilmas (Missouri Univ. Science and Technology), Joseph Graham (Missouri Univ. Science and Technology)
A Predictive Transient Model of the TREAT-SIRIUS Experiments
4:25–4:45PM MDT
Mustafa K. Jaradat (INL), Sebastian Schunert (INL), Frederick N. Gleicher (INL), Vincent M. Laboure (INL), Mark D. DeHart (INL)
Vehicle-Level Performance Benefits of Ammonia Nuclear Thermal Propulsion
4:45–5:05PM MDT
Craig Foulds (Ultra Safe Nuclear), Doug Greisen (Ultra Safe Nuclear), Hari Nagarajan (Ultra Safe Nuclear), Michael Eades (Ultra Safe Nuclear)
Thermal Analysis of the SIRIUS3 Nuclear Propulsion Fuel Calibration Experiment
5:05–5:25PM MDT
Frederick N. Gleicher (INL), Mustafa K. Jaradat (INL), Sebastian Schunert (INL), Mark DeHart (INL)
Presentation Slides (Visible to Attendees) — presentation slides
