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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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!
Latest Magazine Issues
Nov 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Japanese researchers test detection devices at West Valley
Two research scientists from Japan’s Kyoto University and Kochi University of Technology visited the West Valley Demonstration Project in western New York state earlier this fall to test their novel radiation detectors, the Department of Energy’s Office of Environmental Management announced on November 19.
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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