ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
April 2025
Nuclear Technology
March 2025
Fusion Science and Technology
Latest News
Report spotlights energy sector’s growing nuclear investment
As part of a broader series on the future of global energy markets, S&P Global has released a report on examining the growing interest in nuclear power as the solution to many of the problems the energy sector faces.
To read the full details and conclusions of the report, click here.
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)
To access the session recording, you must be logged in and registered for the meeting.
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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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