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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|Computational Thermal Hydraulics
Tuesday, August 22, 2023|10:45AM–12:25PM EDT|Columbia 1
Session Chair:
Chul-Hwa Song (KAERI)
Alternate Chair:
Cheng-Kai Tai (NCSU)
Session Organizer:
Stephen M. Bajorek (USNRC)
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Trace Code Reflood Thermal-Hydraulics Benchmarking Against the NRC-PSU Rod Bundle Heat Transfer (RBHT) Test Facility
10:45–11:05AM EDT
Grant R. Garrett (Penn State), Douglas J. Miller (Penn State), Turki Almudhhi (Penn State), Fan-Bill Cheung (Penn State), Brian R. Lowery (ARL), Molly K. Hanson (ARL), Stephen M. Bajorek (NRC), Kirk Tien (NRC), Chris L. Hoxie (NRC)
Paper
SBLOCA Analysis of Floating Nuclear Reactor Under Ocean Condition Using MARS-KS Moving Reactor Model
11:05–11:25AM EDT
Yujoeng Ko (Seoul Nat'l Univ.), Hyungjoo Seo (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.), Han Rim Choi (KEPCO-ENC)
Implementation of the Homogeneous Equilibrium Model (HEM) into the SAM Code for Two-Phase Flow Modeling
11:25–11:45AM EDT
Michael Gorman (TAMU), Ling Zou (ANL), Rui Hu (ANL), Yassin A. Hassan (TAMU)
Core Damage Extent Analysis of Large-Break LOCA for 4-Loop Pressurized Water Reactor with Detailed 3D Model of Reactor Pressure Vessel and Core
11:45AM–12:05PM EDT
Matthias Jobst (Helmholtz-Zentrum Dresden-Rossendorf), Eduard Diaz-Pescador (Helmholtz-Zentrum Dresden-Rossendorf), Sören Kliem (Helmholtz-Zentrum Dresden-Rossendorf)
Research on Accelerated Methods for Three-Dimensional Nuclear System Analysis Programs
12:05–12:25PM EDT
Ge Li (Xi’an Jiaotong Univ.), Li Huaqi (Northwest Institute of Nuclear Technology), Shan Jianqiang (Xi’an Jiaotong Univ.)
