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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.
Advanced Reactor Safety (ARS)
Technical Session
Wednesday, June 19, 2024|1:00–2:45PM PDT|Palm A
Session Chair:
Koroush Shirvan (MIT)
Session Organizer:
Alternate Chair:
David S. Grabaskas
To access paper attachments, you must be logged in and registered for the meeting.
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Mechanical Aerosol Generation from Two-Phase Flow Pipe Breaks for Low Pressure FHR
1:00–1:20PM PDT
Kyoung M. Kang (Kairos Power), Quan Zhou (Kairos Power), Matthew Denman (Kairos Power), Timothy Drzewiecki (Kairos Power)
Paper
An Examination of Sodium Aerosol Behavior Based on Available Experimental Data
1:20–1:40PM PDT
Tyler Starkus (ANL), Dave Grabaskas (ANL), Dong Hoon Kam (ANL), Shayan Shahbazi (ANL)
Modeling Radionuclide Inventories in MSR Off-Gas Systems with Radiochemical Transport Analysis
1:40–2:00PM PDT
Shayan Shahbazi (ANL), Samuel Walker (INL), Mauricio Tano (INL), Tingzhou Fei (ANL), Yan Cao (ANL), David Grabaskas (ANL)
Implementation of the Sourdough Fuel Cycle and Waste Management Strategy in the EIRENE Novel Molten Salt Reactor Design
2:00–2:20PM PDT
C. Erika Moss (Univ. Tennessee, Knoxville), Ondrej Chvala (Univ. Tennessee, Knoxville), Donny Hartanto (ORNL), John P. Carter (INL)
Advancements in Depletion Modeling for Molten Salt Reactors Using OpenMC: A Case Study with the MSRE
2:20–2:40PM PDT
Lorenzo Chierici (Copenhagen Atomics), Erik Bergbäck Knudsen (Copenhagen Atomics)
Presented by Aslak Stubsgaard (Copenhagen Atomics)
Presentation Slides (Visible to Attendees) — Advancments in Depletion Modeling for Molten Salt Reactors using OpenMC: A Case Study with the MSRE