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Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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August 2026
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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.
13th Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC&HMIT 2023)
Technical Session
Tuesday, July 18, 2023|10:00–11:45AM EDT|301B
Session Chair:
Linyu Lin
Alternate Chair:
Junyung Kim
Session Organizer:
Jamie B. Coble
To access session resources, you must be logged in and registered for the meeting.
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Presentation Slides (Visible to Attendees) — Linyu Lin
Presentation Slides (Visible to Attendees) — Joseph Oncken
Presentation Slides (Visible to Attendees) — Tim Nguyen
Presentation Slides (Visible to Attendees) — Kyle Warns
To access paper attachments, you must be logged in and registered for the meeting.
Adaptive Data-Driven Model Predictive Control for Heat Pipe Microreactors
10:00–10:25AM EDT
Linyu Lin (INL), Benjamin Zastrow (Univ. Texas, Austin), Joseph Oncken (INL), Vivek Agarwal (INL)
Paper
Adaptive Model Predictive Control for Heat-Pipe-Cooled Microreactors Under Normal and Heat Pipe Failure Conditions
10:25–10:50AM EDT
Joseph Oncken (INL), Linyu Lin (INL), Vivek Agarwal (INL)
Presentation Slides (Visible to Attendees)
Design and Prototyping of Diagnostic Methods to Support Autonomous Operations of Advanced Reactors
10:50–11:15AM EDT
Tat Nghia Nguyen (ANL), Akshay J. Dave (ANL), Roberto Ponciroli (ANL), Richard B. Vilim (ANL)
An Interpretation of the Bellman Equation for Risk-Informed Decision Making
11:15–11:40AM EDT
Kyle Warns (Rensselaer Polytechnic Institute), Asad Ullah Amin Shah (Rensselaer Polytechnic Institute), Junyung Kim (Rensselaer Polytechnic Institute), Hyun Gook Kang (Rensselaer Polytechnic Institute)
