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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
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
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
Two updated standards on criticality safety published
The American National Standards Institute (ANSI) recently approved two new American Nuclear Society standards covering different aspects of nuclear criticality safety (NCS).
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Wednesday, June 15, 2022|10:15AM–12:00PM PDT|San Simeon B
Session Chair:
Bao-Wen Yang
Alternate Chair:
Jun Liao
Session Organizer:
W. David Pointer
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Realistic Loss-of-Coolant Accident Analysis of a Boiling Water Reactor for Licensing Base Revision
J. Hagaman (GE Hitachi Nuclear Energy), K. Muftuoglu (GE Hitachi Nuclear Energy), S. Lafountain (GE Hitachi Nuclear Energy), B. Sarikaya (GE Hitachi Nuclear Energy), P. Sharpe (GE Hitachi Nuclear Energy)
Paper
Analysis of Flow Instability Onset in a BWR Rod Bundle Geometry
P. Hurley (Virginia Tech), Y. Liu (Virginia Tech), J.P. Duarte (Virginia Tech), M. Corradini (Univ. Wisconsin, Madison), T. Kozlowski (Univ. Illinois, Urbana-Champaign)
Design Study of CRUD Thermal Properties Characterization Facility DISNY Under Pressurized Water Reactor Normal Operating Condition
Ji Yong Kim (Ulsan Nat'l Institute of Science and Technology), Hyeon Ji Kim (Ulsan Nat'l Institute of Science and Technology), In Cheol Bang (Ulsan Nat'l Institute of Science and Technology)
Two-Phase Flow Upscaling Method in a Macroporous Medium
Tanguy Herry (CEA), Emma Nguyen (CEA), Bruno Raverdy (CEA), Stéphane Mimouni (EDF)
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