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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
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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|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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