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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
2022 ANS Annual Meeting
June 12–16, 2022
Anaheim, CA|Anaheim Hilton
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
June 2022
Nuclear Technology
Fusion Science and Technology
Latest News
Deadline extended to apply for ANS's 2023 ANS Congressional Fellowship
The deadline for applications to the ANS's Glenn T. Seaborg Congressional Science and Engineering Fellowship has been extended. All ANS members are invited to apply to help the Society fulfill its strategic goal of informing nuclear public policy.
All applications and supporting documents are now due by 11:59 p.m. (EDT) on Monday, May 23.
Technical Session|Sponsored by RPD
Wednesday, June 16, 2021|3:30–5:15PM (4:30–6:15PM EDT)
Session Chair:
Blair Bromley (CNL)
Alternate Chair:
Ching-Sheng Lin (INL)
Session Organizer:
Pavel V. Tsvetkov (TAMU)
Staff Producer:
Julie Bry (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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Multi-Group Cross Section Library Generation by FRENDY for Fast Reactor Neutronics Calculations
Go Chiba (Hokkaido Univ.), Akio Yamamoto (Nagoya Univ.), Kenichi Tada (Japan Atomic Energy Agency), Tomohiro Endo (Nagoya Univ.)
Summary
High-Speed Direct Whole-Core Cycle Depletion on Heterogeneous Computing Architectures
Han Gyu Lee (Seoul Nat'l Univ.), Namjae Choi (Seoul Nat'l Univ.), Junsu Kang (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)
Presentation Video
A Direct Comparison of High-Order and Low-Order Neutronics Calculations of the 165 MWth Xe-100 Reactor
Cihang Lu (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.), Eben Mulder (X-Energy), Sonat Sen (X-Energy)
O-SRS: A Refueling and Shuffling Toolkit for Serpent Core Neutronics Analysis
Firas Abdullatif (The Ohio State Univ.), Dean Wang (The Ohio State Univ.)
NucML: Python-Toolbox for ML-Augmented Nuclear Data Evaluations
Pedro Vicente-Valdez (Univ. of California at Berkeley), Lee Bernstein (Univ. of California at Berkeley), Massimiliano Fratoni (Univ. of California at Berkeley)
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