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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|Special Topics
Tuesday, August 22, 2023|1:30–3:10PM EDT|Gunston East/West
Session Chair:
Alessandro Del Nevo (ENEA)
Alternate Chair:
Megan Durse (Westinghouse Electric Co.)
Session Organizer:
Jun Liao (Westinghouse Electric Co.)
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GOTHIC Thermal Hydraulic Analysis of the Passive Heat Removal Facility to Support the Westinghouse Lead Fast Reactor Development
1:30–1:50PM EDT
M.E. Durse (Westinghouse Electric Co.), D.L. Wise (Westinghouse Electric Co.), J. Liao (Westinghouse Electric Co.), R.F. Wright (Westinghouse Electric Co.), C.A. Stansbury (Westinghouse Electric Co.), P. Ferroni (Westinghouse Electric Co.), M. Caramello (Ansaldo Nucleare), A. Wimshurst (Frazer-Nash Consultancy)
Paper
Numerical Analysis and Codes Qualification Based on SIRIO Experiments Within the PIACE Project
1:50–2:10PM EDT
P. Lorusso (ENEA), M. Tarantino (ENEA), F.S. Nitti (ENEA), A. Achilli (SIET), M. Cauzzi (SIET), M. Caramello (Ansaldo Nucleare), T. Hamidouche (SCK CEN), R. Fernandez (SCK CEN), D. Rozzia (SCK CEN), I. Kljenak (Jozef Stefan Institute), R. Krpan (Jozef Stefan Institute), G. Jimenez (Univ. Politécnica de Madrid), C. Queral (Univ. Politécnica de Madrid), T. Del Moro (Sapienza Univ. Rome)
Analysis of Steady State and Operational Transients of the Versatile Loop Facility in Support to Lead Fast Reactor Development
2:10–2:30PM EDT
C. Ciurluini (Sapienza Univ. Rome), M. Principato (Sapienza Univ. Rome), F. Giannetti (Sapienza Univ. Rome), M. Caramello (Ansaldo Nucleare), M. Tarantino (ENEA)
Application Development and Verification of Lead Cooling System Safety Analysis Program based on RELAP5 MOD4.0
2:30–2:50PM EDT
Xiangyang Wang (Lanzhou Univ.), Liu Yang (Lanzhou Univ.), Su Xingkang (Lanzhou Univ.), Qijian Chen (Lanzhou Univ.), Lu Zhang (Chinese Academy of Science), Xianwen Li (Chinese Academy of Science), Bin Han (Southeast Univ.), Aiguo Liu (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer), Bao-Wen Yang (DEQD Institute for Advanced Research in Multiphase Flow and Energy Transfer), Gu Long (Lanzhou Univ.)
