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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Latest News
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
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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