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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|Verification, Validation and Uncertainty Quantification
Wednesday, August 23, 2023|1:30–3:10PM EDT|Embassy
Session Chair:
Lucia Rueda (ENGIE)
Alternate Chair:
Xingang Zhao (ORNL)
Session Organizer:
Joshua Kaizer
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Uncertainty Quantitative Analysis on Sub-channel Code by MCMC Algorithm Based on Bayesian Principle
1:30–1:50PM EDT
Xin He (Shanghai Jiao Tong Univ.), Meiqi Song (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.)
Paper
Attachment
Presentation Video (Visible to Attendees)
BWR Core Thermal-Hydraulic Uncertainty and Sensitivity Analysis with Improved Bypass Modeling Features
1:50–2:10PM EDT
Devshibhai Ziyad (NCSU), Agustin Abarca (NCSU), Maria Avramova (NCSU)
Assessment of Subchannel Analysis Capability of Thermal-Hydraulic System Codes for Detailed Fuel Bundle Simulation
2:10–2:30PM EDT
Yunseok Lee (Incheon Nat'l Univ.), Taewan Kim (Incheon Nat'l Univ.)
Numerical Investigation of Thermal-Hydraulic Behavior During the Reflood Phase Using COSINE Subchannel Code
2:30–2:50PM EDT
Lin Chen (Shanghai Jiao Tong Univ.), Hao Zhang (Shanghai Jiao Tong Univ.), Lixin Du (Shanghai Jiao Tong Univ.), Yingran Guo (Shanghai Jiao Tong Univ.), Yanhua Yang (Shanghai Jiao Tong Univ.), Meng Zhao (Shanghai Jiao Tong Univ.), Yixuan Cheng (Shanghai Jiao Tong Univ.), Zhi Yang (Shanghai Jiao Tong Univ.)
Reflood Experimental Verification and Grid Sensitivity Analysis for COSINE Subchannel Code Based on Two-Fluid Eight Equations
2:50–3:10PM EDT
Yixuan Cheng (Shanghai Jiao Tong Univ.), Lin Chen (Shanghai Jiao Tong Univ.), Hao Zhang (Shanghai Jiao Tong Univ.), Meng Zhao (Shanghai Jiao Tong Univ.), Yanhua Yang (Shanghai Jiao Tong Univ.)
Presentation Video (Visible to Attendees) — NURETH20_40708