ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
April 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
ANS hosts webinar on criticality safety standards
A diagram depicting the NRC’s regulatory structure for nuclear criticality safety. (Image: Oak Ridge National Laboratory)
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series last month. RP3C chair Steven Krahn opened the meeting with brief introductory remarks about the importance of risk-informed, performance based (RIPB) decision-making and the need for new approaches to nuclear design that go beyond conventional and deterministic methods.
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
To access paper attachments, you must be logged in and registered for the meeting.
Register NowLog In
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)
To join the conversation, you must be logged in and registered for the meeting.
