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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Pacific Fusion predicts “1,000-fold leap” in performance, net facility gain by 2030
Inertial fusion energy (IFE) developer Pacific Fusion, based in Fremont, Calif., announced this morning that it is on target to achieve net facility gain—more fusion energy out than all energy stored in the system—with a demonstration system by 2030, and backs the claim with a technical paper published yesterday on arXiv: “Affordable, manageable, practical, and scalable (AMPS) high-yield and high-gain inertial fusion.”
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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