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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Technical Session
Thursday, May 12, 2022|10:00AM–12:00PM EDT|Orchid
Session Chair:
Wes Fuhrman (JHU-APL)
Session Organizer:
Alternate Chair:
Paul Ostdiek (JHU-APL)
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Thermal Performance of a Liquid Metal Heat Pipe with Hybrid Wick Structure
Byung Ha Park (KAERI), Ho Sik Kim (KAERI), Chan Soo Kim (KAERI)
Paper
Computational Sodium Heat Pipe Simulation for Nuclear Reactor Analysis with Nonuniform Incident Temperature
Valerie Lawdensky (Univ. Nevada, Las Vegas), William Culbreth (Univ. Nevada, Las Vegas)
Preliminary Performance Evaluation of Radiator Heat Pipe for Space Nuclear Reactor Application
Ye Yeong Park (Ulsan Nat'l Institute of Science and Technology), Chan Soo Kim (KAERI), In Cheol Bang (Ulsan Nat'l Institute of Science and Technology)
Comparison of Convective Heat Transfer Correlations and Their Application to Nuclear Thermal Propulsion Reactors
Dennis Nikitaev (Analytical Mechanics Assoc.), Corey D. Smith (Analytical Mechanics Assoc.), Kelsa Palomares (Analytical Mechanics Assoc.)
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