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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.
18th International Probabilistic Safety Assessment and Analysis (PSA 2023)
Technical Session|PSA Analyses: Methods and Applications
Thursday, July 20, 2023|8:00–9:30AM EDT|300A
Session Chair:
Michelle Bensi (University of Maryland)
Alternate Chair:
Michael D. Muhlheim
Session Organizer:
Askin Guler Yigitoglu (ORNL)
To access paper attachments, you must be logged in and registered for the meeting.
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Probabilistic Risk Assessment of a Light-Water Reactor Coupled with a High-Temperature Electrolysis Hydrogen Production Plant
8:00–8:25AM EDT
Robby Christian (INL), Courtney Otani (INL), Kurt Vedros (INL), Austin M. Glover (Sandia)
Paper
Risk-Informed Design Process of Emergency Core Cooling System in the Floating Nuclear Power Plants
8:25–8:50AM EDT
Changhong Peng (Univ. Science and Technology of China), Xinyan Xu (Univ. Science and Technology of China), Lanxin Gong (Univ. Science and Technology of China)
PACE Level 3 PSA Code -- Developments to Account for Radiosensitivity Dependence on Age and Sex of Health Effects and Impact of High Spatial and Temporal Resolution Population Estimates
8:50–9:15AM EDT
Thomas Charnock (United Kingdom Health Security Agency), Kelly Jones (United Kingdom Health Security Agency), Antony Bexon (United Kingdom Health Security Agency)
Application of Probabilistic Safety Assessment Within an Integrated Safety Approach for Re-Design of the Nuclear Island During Post-Operational Phase
9:15–9:40AM EDT
Filip Van Opstal (Tractebel ENGIE), Federico Agosti (Tractebel ENGIE)
