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Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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August 2026
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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.
Advanced Reactor Safety (ARS)
Technical Session
Monday, June 17, 2024|1:00–2:45PM PDT|Palm A
Session Chair:
Matthew R. Denman
Session Organizer:
Alternate Chair:
Koroush Shirvan
To access paper attachments, you must be logged in and registered for the meeting.
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Quantification of In-Containment Mechanistic Source Term for Advanced Light Water Reactor
1:00–1:20PM PDT
Yahya A. Alzahrani (NCSU), Mihai A. Diaconeasa (NCSU)
Paper
An Assessment of the Applicability and Usability of Light Water Reactor Source Term Software for Non-Light Water Reactor Designers
1:20–1:40PM PDT
Matthew R. Denman (Kairos Power), Peiwen T. Whysall (Kairos Power), Jordan E. Hagaman (Kairos Power)
The Development of Simplified Radionuclide Transport Code (SRT) Version 2.1
1:40–2:00PM PDT
Tyler Starkus (ANL), Dave Grabaskas (ANL), Dong Hoon Kam (ANL), Shayan Shahbazi (ANL)
Consequence Uncertainty Quantification in LMP Applications
2:00–2:20PM PDT
Matthew Humberstone (U.S. Nuclear Regulatory Commission), Hanh Phan (U.S. Nuclear Regulatory Commission), Steven Unwin (PNNL), Steve Short (PNNL), Garill Coles (PNNL)
Presented by Jeffery Wood (U.S. Nuclear Regulatory Commission)
Presentation Slides (Visible to Attendees)
Oxidation Model of the Accident Tolerant Fuel Implemented in NuScale Reactor Using MELCOR Code
2:20–2:40PM PDT
Mohammad Amer Allaf (Univ. Wisconsin, Madison), Grace Ejnik (Univ. Wisconsin, Madison), WooHyun Jung (Univ. Wisconsin, Madison), Michael Corradini (Univ. Wisconsin, Madison), Koroush Shirvan (MIT), Juliana Pacheco Duarte (Univ. Wisconsin, Madison)
