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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!
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
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.
Technical Session|Sponsored by RPD
Wednesday, June 16, 2021|4:30–6:15PM EDT
Session Chair:
Blair Bromley (CNL)
Alternate Chair:
Ching-Sheng Lin (INL)
Session Organizer:
Pavel V. Tsvetkov (TAMU)
Staff Producer:
Julie Bry (ANS)
This is a standing RPD session with papers on all reactor analysis topics of contemporary interest.
To access the session recording, you must be logged in and registered for the meeting.
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Multi-Group Cross Section Library Generation by FRENDY for Fast Reactor Neutronics Calculations
Go Chiba (Hokkaido Univ.), Akio Yamamoto (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency), Tomohiro Endo (Nagoya Univ.)
Paper
High-Speed Direct Whole-Core Cycle Depletion on Heterogeneous Computing Architectures
Han Gyu Lee (Seoul Nat'l Univ.), Namjae Choi (Seoul Nat'l Univ.), Junsu Kang (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)
Presentation Video (Visible to Attendees)
A Direct Comparison of High-Order and Low-Order Neutronics Calculations of the 165 MWth Xe-100 Reactor
Cihang Lu (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.), Eben Mulder (X-Energy), Sonat Sen (X-Energy)
O-SRS: A Refueling and Shuffling Toolkit for Serpent Core Neutronics Analysis
Firas Abdullatif (The Ohio State Univ.), Dean Wang (The Ohio State Univ.)
NucML: Python-Toolbox for ML-Augmented Nuclear Data Evaluations
Pedro Vicente-Valdez (Univ. of California at Berkeley), Lee Bernstein (Univ. of California at Berkeley), Massimiliano Fratoni (Univ. of California at Berkeley)
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