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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
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
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|Water-Cooled Reactor Operations and Accident Analysis
Monday, August 21, 2023|1:30–3:10PM EDT|Columbia 3/4
Session Chair:
Caleb Brooks (Univ. Illinois, Urbana-Champaign)
Alternate Chair:
Hyun Sik Park
Session Organizer:
Cesare Frepoli
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BWRX-300 Chimney Evaluations (1): Conceptual Design of the Chimney
1:30–1:50PM EDT
Charles Heck (Global Nuclear Fuel), Scott Bowman (Global Nuclear Fuel), Kazuaki Kito (Hitachi-GE Nuclear Energy)
Paper
Presentation Slides (Visible to Attendees) — presentation paper #40308
BWRX-300 SMR Chimney Evaluations (2): Strategy for Qualifying TRACG Evaluations of Chimney Void Fractions
1:50–2:10PM EDT
A. Povolny (Hitachi-GE Nuclear Energy), K. Katono (Hitachi-GE Nuclear Energy), C. Heck (Global Nuclear Fuel), Z. Zhang (GE Hitachi Nuclear Energy)
Presentation Slides (Visible to Attendees)
BWRX-300 SMR Chimney Evaluations (3): HUSTLE Testing in Large Diameter Chimney at Nominal Pressure and Temperature
2:10–2:30PM EDT
Kenichi Katono (Hitachi-GE Nuclear Energy), Antonin Povolny (Hitachi-GE Nuclear Energy), Hajime Furuichi (Hitachi-GE Nuclear Energy), Kiyoshi Fujimoto (Hitachi-GE Nuclear Energy), Kenichi Yasuda (Hitachi-GE Nuclear Energy), Kazuaki Kito (Hitachi-GE Nuclear Energy)
BWRX-300 SMR Chimney Evaluations (4): Measurement of Void Fraction and Velocity Distributions in Large Diameter Chimney at Nominal Pressure and Temperature Using Double-Plane Wire-Mesh Sensor
2:30–2:50PM EDT
Hajime Furuichi (Hitachi-GE Nuclear Energy), Antonin Povolny (Hitachi-GE Nuclear Energy), Kenichi Katono (Hitachi-GE Nuclear Energy), Kenichi Yasuda (Hitachi-GE Nuclear Energy), Kazuaki Kito (Hitachi-GE Nuclear Energy)
Attachment
Feasibility Analysis of Flooding Safety System of i-SMR with MELCOR Code
2:50–3:10PM EDT
Chang Hyun Song (Hanyang Univ.), Jae Hyung Park (Hanyang Univ.), Sung Joong Kim (Hanyang Univ.)
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