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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
Friday, December 3, 2021|3:05–4:50PM EST |Columbia 4
Session Chair:
Zeyun Wu (VCU)
Alternate Chair:
Massimiliano Fratoni
Session Organizer:
Student Assistant:
K. Lisa Reed
To access the session recording, you must be logged in and registered for the meeting.
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To access paper attachments, you must be logged in and registered for the meeting.
Revisit of the Dancoff-Based Wigner-Seitz Approximation for Pointwise and Multigroup Resonance Self-Shielding Calculations in SCALE
3:10–3:30PM EST
Kang Seog Kim (ORNL), Andrew M. Holcomb (ORNL), Matthew A. Jessee (ORNL), William A. Wieselquist (ORNL)
Paper
Serpent/PARCS Calculation for VVER-1000 Core with TriPEN-9 Method
3:30–3:50PM EST
Muhammad Rizki Oktavian (Purdue Univ.), Oscar Lastres (Purdue Univ.), Yunlin Xu (Purdue Univ.)
In-situ APEC Leakage Correction Based on 2x2 Nodal Analysis for 2-D Macroscopic Depletion Calculation
3:50–4:10PM EST
Seongdong Jang (KAIST), Yonghee Kim (KAIST)
An Introduction to REX: A Fuel-Clad Thermo-Mechanical Analysis Tool for Advanced Reactor Concepts
4:10–4:30PM EST
Nicholas J. Fassino (Georgia Institute of Technology), Anna Erickson (Georgia Institute of Technology)
A Feasibility Study of SPH Factors for a Heterogeneous Geometry Problem
4:30–4:50PM EST
Zhaopeng Zhong (ANL), Changho Lee (ANL)
