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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 RPD
Tuesday, November 11, 2025|3:15–5:00PM EST|Georgetown East
Session Chair:
Akio Yamamoto (Nagoya Univ.)
Alternate Chair:
Zeyun Wu
Session Organizer:
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Nonlinear Diffusion Acceleration with Local Discontinuous Galerkin Method
3:15–3:35PM EST
Rikuto Kasama (Nagoya University), Akio Yamamoto (Nagoya University), Tomohiro Endo (Nagoya University)
Paper
Reduced Order Model for Temporal Evolution of Nuclide Number Densities after Burst Fission (1) Proper Orthogonal Decomposition and Gelarkin Projection
3:35–3:55PM EST
Go Chiba (Hokkaido University), Kosuke Tsujita (University of Fukui), Tatsuya Fujita (Hokkaido University), Shuhei Miwa (Nuclear Engineering Ltd.)
Reduced Order Model for Temporal Evolution of Nuclide Number Densities after Burst Fission (2) Estimation from Reduced Nuclide Transmutation Chain Result
3:55–4:15PM EST
Junki Masuda (Hokkaido University), Go Chiba (Hokkaido University), Sota Endo (Hokkaido University), Tatsuya Fujita (Hokkaido University)
On Performance of Acceleration Methods for Multi-Group Discrete-Ordinate Neutron Transport Calculations on Block-Type Gas-Cooled Reactor
4:15–4:35PM EST
Go Chiba (Hokkaido University), Tatsuya Fujita (Hokkaido University)
Comparative Study of Nodal and Pin-by-Pin Methods for APR1400 Core Analysis
4:35–4:55PM EST
Seyeon Hwang (KEPCO International Nuclear Graduate School), Jinsun Kim (KEPCO Nuclear Fuel Co. Ltd.), Jooil Yoon (KEPCO International Nuclear Graduate School)
