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Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
Technical Session|Sponsored by RPD
Monday, June 14, 2021|3:15–5:00PM EDT
Session Chair:
Pavel V. Tsvetkov (TAMU)
Session Organizer:
Alternate Chair:
Massimiliano Fratoni
Staff Producer:
Ashley Jiminian (ANS)
This is a standing RPD session with papers on all reactor analysis topics of contemporary interest.
To access the session recording, you must be logged in and registered for the meeting.
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To access paper attachments, you must be logged in and registered for the meeting.
Multiphysics Benchmark Results from Moltres
Sun Myung Park (Univ. of Illinois Urbana-Champaign), Kathryn D. Huff (Univ. of Illinois Urbana-Champaign)
Paper
Cerberus: A MOOSE-Based Application for Solving the SP3 Equations
Roberto E. Fairhurst Agosta (Univ. of Illinois at Urbana-Champaign), Kathryn D. Huff (Univ. of Illinois Urbana Champaign)
Verification of the Multi-Group Generation Capability of FRENDY Nuclear Data Processing Code for Recent Nuclear Data through Comparison of One-group Reaction Rates
Akio Yamamoto (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency), Go Chiba (Hokkaido Univ.), Tomohiro Endo (Nagoya Univ.)
Large-Scale Whole-Core Monte Carlo Cycle Depletion Employing GPUs
Kyung Min Kim (Seoul Nat'l Univ.), Namjae Choi (Seoul Nat'l Univ.), Han Gyu Lee (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)
Presentation Video (Visible to Attendees)
Validation of SCALE 6.2.4 and ENDF/B-VII.1 Data Libraries for Nuclide Inventory Analysis in PWR Used Fuel
Germina Ilas (ORNL), Briana Hiscox (ORNL)
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