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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.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Tuesday, June 14, 2022|1:00–2:45PM PDT|Redondo
Session Chair:
Subash Sharma (UMass Lowell)
Alternate Chair:
Trevor Howard (Oregon State)
Session Organizers:
Matthew D. Zimmer (Naval Nuclear Lab)
Xu Wu (NCSU)
To access paper attachments, you must be logged in and registered for the meeting.
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CFD Analysis of the Sodium-Water Reaction in the Minichannel of PCSG Designed for SFR
Taewoo Kim (Korea Univ. Science and Technology), Hyun-Sik Park (KAERI), Sang Ji Kim (KAERI)
Paper
A Multiphysics Framework Using High Resolution DNS to Optimize Conditions for Plasma Formation
Naveen Pillai (NCSU), Nicholas L. Sponsel (NCSU), Katharina Stapelmann (NCSU), Igor A. Bolotnov (NCSU)
A Conceptual Study of Air Curtain on the Reactor Vessel Auxiliary Cooling System
Jaejin Choi (KAIST), Yong Hoon Jeong (KAIST)
Development of Integrated Safety Analysis Code with Capability of Detailed Simulation for Multiple Fuel Rods
Yunseok Lee (Incheon National Univ.), Jaeseung Suh (SenTech Co.), Taewan Kim (Incheon National Univ.)
LES of Natural Convection Along the Vertical Wall Applied for the Scale of Small Modular Reactor ( Ra*≈10^19)
Songzhi Yang (CEA), Ulrich Bieder (CEA)
