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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nuclear Science and Engineering
January 2026
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December 2025
Fusion Science and Technology
November 2025
Latest News
Standard Nuclear executes OTA with DOE
Reactor-agnostic TRISO fuel producer Standard Nuclear recently announced that it has executed an other transaction agreement (OTA) with the Department of Energy. As one of the five companies involved in the DOE’s Fuel Line Pilot Program, its entrance into this deal marks a milestone in the public-private effort to bring advanced fuel production on line in support of the DOE’s concurrently running Reactor Pilot Program.
Technical Session|Sponsored by IRD
Tuesday, November 17, 2020|4:50–6:30PM EST
Session Chair:
Jeremy Licht (ANL)
Alternate Chair:
Walid Mohamed (ANL)
Session Organizers:
Erik Wilson (ANL)
Lin-Wen Hu
Track Organizer:
Staff Producer:
Rick Michal (American Nuclear Society)
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Computational Software Developed by RERTR for the Conversion of Research and Test Reactors to LEU Fuel
Jeremy R. Licht (ANL), Erik H. Wilson (Argonne National Laboratory), Arne P. Olson (ANL)
Paper
Reactor Analysis Code Benchmark to AFIP-7 Experiment
Erik H. Wilson (Argonne National Laboratory), Walid Mohamed (Argonne National Laboratory), David Jaluvka (Argonne National Laboratory), Micheal A. Smith (Argonne National Laboratory), Lara M. Peguero (Argonne National Laboratory), John A. Stillman (Argonne National Laboratory)
The ADDER Software for Reactor Depletion and Fuel Management Analysis
John A. Stillman (Argonne National Laboratory), Erik H. Wilson (Argonne National Laboratory), Florent Heidet (Argonne National Laboratory), Adam G. Nelson (Argonne National Laboratory)
From CFD Simulation to Hot Channel Factor Estimation for the Conversion of Involute Plate Research Reactor
Yiqi Yu (Argonne National Laboratory)
Assessment of Reactor Kinetics Capability in RELAP5/MOD3.3 and PARET/ANL V7.6 to Support the Conversion of the University of Missouri Research Reactor to Low-Enriched Uranium Fuel
L. P. Foyto (University of Missouri-Columbia Research Reactor), K. Kutikkad (University of Missouri-Columbia Research Reactor), E. H. Wilson (Argonne National Laboratory), E. E. Feldman (Argonne National Laboratory), J. A. Stillman (Argonne National Laboratory), Dhongik S. Yoon (Argonne National Laboratory)
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