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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
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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