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
NRC to add new items to categorical exclusions list
The Nuclear Regulatory Commission has identified five categories of action to add to its list of categorical exclusions to reduce its documentation work under National Environmental Policy Act (NEPA) procedures.
These revisions are included in the final rule, “Categorical exclusions from environmental review,” which was published in the Federal Register on March 30. The final rule will become effective on April 29.
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.