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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Nuclear progress, but not much else, from COP29
COP29 was good for nuclear energy, but not so good for anything else.
That was one of Seth Grae’s takeaways from this year’s Conference of the Parties—or, United Nations Framework Convention on Climate Change (UNFCCC)—held for two weeks in November in Baku, Azerbaijan. Grae, chief executive of Lightbridge Corporation and chair of the American Nuclear Society’s International Council, attended with four other ANS delegates: ANS President Lisa Marshall, Gale Hauck, Shirly Rodriguez, and Andrew Smith.
Technical Session|Experimental Thermal Hydraulics
Wednesday, August 23, 2023|9:00–10:20AM EDT|Columbia 1
Session Chair:
Yue Jin (UM)
Alternate Chair:
Saya Lee (PSU)
Session Organizer:
Xiaodong Sun
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Coal Experiments Investigating the Reflooding of a 7 X 7 Rods Bundle During a Loss of Coolant Accident -- Effect of a Partially Blocked Area with Ballooned Rods
9:00–9:20AM EDT
G. Repetto (IRSN), Q. Grando (IRSN), B. Bruyère (IRSN), S. Eymery (IRSN), R. Fortman (STERN Laboratories), R. Van Lochem (STERN Laboratories)
Paper
Experimental Investigation of Minimum Film Boiling Temperature During Reflood Transients
9:20–9:40AM EDT
Turki K. Almudhhi (Penn State), Douglas J. Miller (Penn State), Grant R. Garrett (Penn State), Ian R. Lowery (Penn State), Fan-Bill Cheung (Penn State), Brian R. Lowery (Penn State), Stephen M. Bajorek (U.S. Nuclear Regulatory Commission), Kirk Tien (U.S. Nuclear Regulatory Commission), Chris L. Hoxie (U.S. Nuclear Regulatory Commission)
Spray Cooling of a Rod Bundle with a Counter-Current Steam Flow in Spent Fuel Pool Conditions
9:40–10:00AM EDT
G. Brillant (IRSN)
Uniform and Non-Uniform Flows Through a PWR-Type Rod Bundle with Mixing Grids at Reynolds Number Ranging from 800 up to 70000: Pressure Loss Measurements
10:00–10:20AM EDT
Clément Melin (CEA), Gilles Bernard-Michel (CEA), Benjamin Cariteau (CEA), Philippe Fillion (CEA)
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