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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
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!
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The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Workshop
Sunday, April 21, 2024|1:00–5:00PM PDT|Franciscan B
Price: $49
Westinghouse Electric Company recognizes the importance of supporting students pursuing a career in reactor physics. For this reason, Westinghouse will be sponsoring the first 100 student workshop registrants by covering their fees. Contact registrar@ans.org for a discount code before registering. Limited space available in each workshop. Once these seats are filled, you will be put on a waitlist. You must request a discount code before registering. No refunds will be made if you do not contact us before registering.
Organized by Ting Fei (ANL), Mustafa Jaradat (INL), Mauricio Tano Retamales (ANL) through the Advanced Reactor Technology and Nuclear Energy Advanced Modeling and Simulation Programs
The goal of the training session is to demonstrate the application of MOOSE-based tools for coupled neutronics – thermal-hydraulics modeling of liquid fuel molten salt reactors (MSRs). The training session will be focused on developing a multiphysics model for a simplified model of the Molten Salt Reactor Experiment (MSRE) by coupling neutronics based on the Griffin neutronics code, and thermal hydraulics based on Pronghorn/SAM codes. Steady-state and a flow driven transient will be modeled with demonstration of the delayed neutron precursor impacts.
The training will be conducted via the INL High Performance Computing (HPC) center. Trainees can either apply for: A) an INL HPC account and code licenses directly via (https://inl.gov/ncrc/) or B) temporary INL HPC account and temporary access to the codes. Either way, details on the INL’s Nuclear Computational Resource Center training signup process will be shared with registered participants. Trainees must bring their own laptops. Details on the process will be shared with registered participants. Note the following cutoffs for INL HPC account and license applications:
Cutoff for U.S.A. nationals INL HPC account and licenses is April 15th, 2024.
Cutoff for foreign nationals INL HPC account and licenses is March 1st, 2024.
Agenda:
1:00 – 1:15 pm (15 min): Introduction to MSRE
1:15 – 1:30 pm (15 min): Introduction to cross section preparation for MSRE
1:30 – 1:45 pm (15 min): MSRE mesh generation
1:45 – 2:15 pm (30 min): Steady-state/Stationary neutronics model of MSRE with Griffin
2:15 – 2:45 pm (30 min): MSRE Thermal model of MSRE with Griffin Pronghorn
2:45 – 3:15 pm (30 min): Steady-state/Flowing neutronics modeling of MSRE coupled
3:15 – 3:30 pm (15 min): Coffee Break
3:30 – 4:30 pm (60 min): Multiphysics transient modeling of MSRE with Griffin/Pronghorn
4:30 – 5:00 pm (30 min): Species transport in MSRE (Griffin, Pronghorn, & Thermochimica)
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