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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
Monday, May 16, 2022|3:30–5:15PM EDT|Ellwood
Session Chair:
Charles A. Wemple
Alternate Chair:
Kurt A. Dominesey
Session Organizer:
Akio Yamamoto
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Linear Source Method of Characteristics in HELIOS2
Charles A. Wemple (Studsvik Scandpower), Rodolfo M. Ferrer (Studsvik Scandpower)
Paper
Performance Enhancement of Planar MOC Calculation in Hexagonal Geometries by Assembly-Wise Domain Decomposition
Seongchan Kim (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)
Neutron Diffusion Calculation in Heterogeneous Geometry Based on Local/Global Iteration Using Proper Orthogonal Decomposition
Masato Ito (Nagoya Univ.), Tomohiro Endo (Nagoya Univ.), Akio Yamamoto (Nagoya Univ.), Yoshitada Masaoka (Nuclear Fuel Industries), Yasuhiro Kodama (Nuclear Fuel Industries), Hiroaki Nagano (Nuclear Fuel Industries)
Presentation Video (Visible to Attendees) — Neutron Diffusion Calculation in Heterogeneous Geometry Based on Local/Global Iteration Using Proper Orthogonal Decomposition
Reduced-Order Modeling of Neutron Transport Separated in Energy by Minimax Proper Generalized Decomposition
Kurt Dominesey (Rensselaer Polytechnic Institute), Wei Ji (Rensselaer Polytechnic Institute)
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