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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
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.
