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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
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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|Sponsored by THD
Tuesday, June 15, 2021|4:30–6:15PM EDT
Session Chair:
Sang J. Kim
Session Organizer:
Alternate Chair:
Xiaodong Sun
Staff Producer:
Jessie Vazquez (ANS)
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Thermal Fatigue Assessment of Printed Circuit Steam Generator Induced by Dryout Front Oscillation
Jin Su Kwon (KAIST), Jeong Ik Lee (KAIST), Sang Ji Kim (KAERI)
Paper
Development of Thermal-Hydraulic Test Requirements of an Integral Reactor PCSG
Joo Hyung Moon (KAERI), Hyunjun Cho (KAERI), Cheong Bong Chang (KAERI)
Study of Microchannel Two-Phase Flow CFD Modeling for PCSG TH Performance Analysis
Sung Gil Shin (KAIST), Jin Su Kwon (KAIST), Jeong Ik Lee (KAIST), Sang Ji Kim (KAERI)
Characteristics of the Sodium-Water Reaction Phenomena in the PCSG
Taewoo Kim (Univ. of Science and Technology), Sang Ji Kim (KAERI)
Thermal-Hydraulic Design and Scale Analysis for an Integral Reactor PCSG
Hun Sik Han (KAERI), Seok Kim (KAERI), Sang Ji Kim (KAERI)
Molecular Dynamics Simulations for Fouling Phenomena in Printed-Circuit Steam Generators and Heat Exchanger: A Preliminary Study
Takuji Oda (Seoul National Univ.), Junhyoung Gil (Seoul National Univ.), Sehyeok Park (Seoul National Univ.)
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