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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|New and Advanced Reactors
Wednesday, August 23, 2023|10:45AM–12:25PM EDT|Gunston East/West
Session Chair:
Jun Liao (Westinghouse Electric Co.)
Alternate Chair:
Piyush Sabharwall
Session Organizer:
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Investigation of Hybrid Heat Pipe Shutdown Rod Concept of Microreactor as a Passive Safety System
10:45–11:05AM EDT
Dong Hun Lee (Ulsan Nat'l Institute Science and Technology), In Cheol Bang (Ulsan Nat'l Institute Science and Technology)
Paper
Thermal Stress Analysis for Heat Pipe Cooled Microreactor Core Varying Condenser Temperature
11:05–11:25AM EDT
Myung Jin Jeong (Seoul Nat'l Univ.), San Lee (Seoul Nat'l Univ.), Jaeuk Im (Seoul Nat'l Univ.), Hyoung Kyu Cho (Seoul Nat'l Univ.)
Experimental Study on the Start-up Characteristics and Performance of a Ten Sodium Heat Pipe Bundle Array
11:25–11:45AM EDT
Pei-Hsun Huang (Univ. Michigan), Taehwan Ahn (Univ. Michigan), Annalisa Manera (Univ. Michigan), Victor Petrov (Univ. Michigan)
Nuclear Spaceship for Interplanetary Cruise Using a Micro Fast Reactor
11:45AM–12:05PM EDT
Tadashi Narabayashi (Tokyo Institute of Technology)
Study on Startup Characteristic of a Supercritical Carbon Dioxide Brayton Cycle Coupled with Heat Pipe Cooled Reactor
12:05–12:25PM EDT
Zheng Wang (Xi’an Jiaotong Univ.), Minghui Zhang (Xi’an Jiaotong Univ.), Shihao Xu (Xi’an Jiaotong Univ.), Junli Gou (Xi’an Jiaotong Univ.), Jianqiang Shan (Xi’an Jiaotong Univ.)
Presentation Video (Visible to Attendees)
