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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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January 2025
Nuclear Technology
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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Technical Session|Sponsored by THD
Wednesday, November 18, 2020|12:00–2:10PM EST
Session Chair:
Dillon R. Shaver
Alternate Chair:
Elia Merzari (Penn State)
Session Organizer:
Igor A. Bolotnov (NCSU)
Staff Producer:
Erica McGowan (American Nuclear Society)
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Verification of Transient Simulations Using the SAS4A/SASSYS-1 Coupled Channel Interface
Daniel O'Grady (Argonne National Laboratory), Guanheng Zhang (Argonne National Laboratory), Thomas H. Fanning (Argonne National Laboratory), Rui Hu (Argonne National Laboratory), Guojun Hu (Argonne National Laboratory), Thanh Q. Hua (Argonne National Laboratory), Acacia J. Brunett (Argonne National Laboratory)
Paper
Joint SAS4A/SASSYS-1 Development for Lead Cooled Fast Reactor Safety Analysis
Anton Moisseytsev (ANL), Thomas H. Fanning (ANL), Daniel O’Grady (ANL), Thanh Quoc Hua (ANL), Adrian M. Tentner (ANL), Aydin Karahan (ANL), Acacia J. Brunett (ANL), Tanju Sofu (ANL), Michael Epstein (Fauske & Associates, LLC), Sung Jin Lee (Fauske & Associates, LLC), Daniel L. Wise (Westinghouse Electric Co.), Paolo Ferroni (Westinghouse Electric Co.), Jun Liao (Westinghouse Electric Company)
Implementation of an Extended Reactor Vessel Heat Rejection Modeling Capability in SAS4A/SASSYS-1
Thomas H. Fanning (Argonne National Laboratory), Acacia J. Brunett (Argonne National Laboratory), Daniel O'Grady (Argonne National Laboratory)
NekRS: Massively parallel fluid flow simulations in reactor cores
Elia Merzari (Pennsylvania State University), Misun Min (Argonne National Laboratory), Yu-Hsiang Lan (Argonne National Laboratory), Stefan Kerkemeier (Argonne National Laboratory), Paul Fischer (University of Illinois)
Statistical Uncertainties of Passive Scalars in a Direct Numerical Simulation of Low-Prandtl Fluid Flow over a Backward Facing Step
Iztok Tiselj (Jožef Stefan Institute), Jure Oder (Jozef Stefan Institut)
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