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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|Sponsored by MSTD
Monday, June 13, 2022|1:00–2:45PM PDT|Malibu
Session Chair:
Annabelle Le Coq (ORNL)
Alternate Chair:
Troy Munro
Session Organizer:
Kenneth J. Geelhood
To access paper attachments, you must be logged in and registered for the meeting.
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Compatibility of 316H in Static and Flowing FLiBe and FLiNaK Salts at 550°-650°C
D. Sulejmanovic (ORNL), B.A. Pint (ORNL), M. Lance (ORNL), Y.F. Su (ORNL), J.R. Keiser (ORNL)
Paper
Analysis of High Nickel Alloys Partially Submerged in a Ternary Chloride Salt
Aaron Overacker (Univ. New Mexico), Kenneth Armijo (Sandia), Dimitri Madden (Sandia), Patrick Burton (Sandia), Minghui Chen (Univ. New Mexico)
Development of Crystal Whisker Structures in Ternary Molten Chloride Salt Exposed Haynes 230
Dimitri Madden (Sandia), Aaron Overacker (Sandia), Kenneth M. Armijo (Sandia), Patrick Burton (Sandia)
A Combined Experimental-Computational Approach to Design Corrosion Resistant Alloys for Molten Salt Reactors
R. Pillai (ORNL), C. Parker (ORNL), D. Sulejmanovic (ORNL), B.A. Pint (ORNL)
Design of Natural Circulation Molten Salt Loop to Study Long-Term Corrosion Effects of NaF-BeF2 on SS316H in Argon Glovebox Environment
Michael A. Borrello (Univ. California, Berkeley), Christian M. Sclafani (Univ. California, Berkeley), Raluca O. Scarlat (Univ. California, Berkeley)
