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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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Apr 2025
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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).
Technical Session
Thursday, May 19, 2022|8:00–9:45AM EDT|Haselton
Session Chair:
Baocheng Zhang (Westinghouse Electric Co.)
Session Organizer:
Alternate Chair:
Petri Guimaraes (Studsvik Scandpower)
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Comparison of CASMO-5, MPACT and Serpent 2 for the Modeling of Advanced BWR Lattices
M. Hursin (Paul Scherrer Institute), P. Mala (Paul Scherrer Institute), A. Vasiliev (Paul Scherrer Institute), H. Ferroukhi (Paul Scherrer Institute), Yuxuan Liu (Univ. Michigan), Sooyoung Choi (Univ. Michigan), Brendan Kochunas (Univ. Michigan)
Paper
Demonstration of an Embedded Diffusion Scheme for Modelling the BEAVRS Benchmark Problem
R. H. Prinsloo (Necsa), S.A. Groenewald (Necsa), C. Jacobs (Necsa), D.I. Tomašević (Necsa)
Presented by Kostadin Ivanov (NCSU)
Development and Validation of the GNF Core Simulator Package LANCR02/PANAC11 for the Evaluation of Boiling Water Reactors with LEU+ and High Burn-up Fuel Characteristics
J. Hannah (Global Nuclear Fuel), K. Bennett (Global Nuclear Fuel), G. Cuevas-Vivas (Global Nuclear Fuel), J. Finch (Global Nuclear Fuel), F. Jones (Global Nuclear Fuel), L. Pogosbekyan (Global Nuclear Fuel), B. Ward (Global Nuclear Fuel)
Fuel Cycle Depletion to Spent Fuel Gamma Facility Dose Rate Validation Studies
D. Chandler (ORNL)
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