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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Apr 2025
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
The 2025 ANS election results are in!
Spring marks the passing of the torch for American Nuclear Society leadership. During this election cycle, ANS members voted for the newest vice president/president-elect, treasurer, and six board of director positions (four U.S., one non-U.S., one student). New professional division leadership was also decided on in this election, which opened February 25 and closed April 15. About 21 percent of eligible members of the Society voted—a similar turnout to last year.
Technical Session|Experimental Thermal Hydraulics
Wednesday, August 23, 2023|10:45AM–12:25PM EDT|Cardozo
Session Chair:
Guanyu Su (UCB)
Session Organizer:
Bao-Wen Yang (DEDQ)
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Experimental Investigations of Material-Conjugated Subcooled Flow Boiling
10:45–11:05AM EDT
Mingfu He (Univ. New Mexico), Minghui Chen (Univ. New Mexico)
Paper
The Effect of Time Varying Axial Power Shape on Transient Critical Power Performance of BWR Fuel
11:05–11:25AM EDT
B. Ward (Global Nuclear Fuel Americas), S. Oh (Global Nuclear Fuel Americas), J. Andersen (Global Nuclear Fuel Americas), C. Heck (Global Nuclear Fuel Americas), D. Rock (Global Nuclear Fuel Americas), M. Sugawara (Global Nuclear Fuel Americas), J. Lamy (Global Nuclear Fuel Americas)
Presentation Slides (Visible to Attendees)
Steady-State and Power Transient Critical Heat Flux Experiments of FeCrAl and Zircaloy Claddings Under Saturated Pool Boiling
11:25–11:45AM EDT
Experimental Research About Corrosion Effect on Boiling Heat Transfer Performance of Plate-Type Samples with Micro-Structures
11:45AM–12:05PM EDT
Wei Xu (Shanghai Jiao Tong Univ.), Xiaojing Liu (Shanghai Jiao Tong Univ.), Kun Ouyang (Shanghai Jiao Tong Univ.), Xiaoqiang He (Nuclear Power Institute of China)
Presentation Video (Visible to Attendees) — Wei Xu
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