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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
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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