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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Jun 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Technical Session|Sponsored by RPD
Wednesday, June 16, 2021|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.)
Paper
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 (Visible to Attendees)
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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