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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.
Jong Woon Kim, Cheol Woo Lee, Young-Ouk Lee, Dong-Won Lee, Seungyon Cho
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 652-656
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-966
Articles are hosted by Taylor and Francis Online.
The discrete ordinates code under development by KAERI uses an unstructured tetrahedral mesh, and can thus be applied to solve the radiation transport in a complicated geometry. In addition, the geometry modeling process has become much easier because computational tetrahedral meshes are generated based on the CAD file by Gmsh. This program has been enhancing its performance and adding functions for each application.
In previous research, it was applied in a neutronics analysis for the Korea Helium Cooled Ceramic Reflector (HCCR) TBM. The total neutron fluxes were compared with the results from MCNPX and showed good agreement.
In this paper, we applied our program to a simplified ITER model which is a 40-degree toroidal segment. The zone averaged total fluxes were compared with those of MCNPX, and total neutron flux distribution was visualized in a three-dimensional system domain.
