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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
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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Daniel Nunez, Benedikt Krohn, Victor Petrov, Annalisa Manera (Univ of Michigan)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 904-918
Over recent decades, Particle Image Velocimetry (PIV) has become an increasingly common optical technique used to study fluid flows. As a result, large quantities of PIV data are becoming readily available for the development and validation of Computational Fluid Dynamics (CFD) codes. The CFD community heavily relies on experimental data, and the experimental community should focus on an important quality that is often overlooked – the repeatability and the reproducibility of PIV data. Unfortunately, with advanced instrumentation such as a PIV system, slight variations in equipment setup can be sources of discrepancies in the measurements. In the present work, we discuss the level of repeatability and reproducibility of PIV results obtained in the Reactor Cavity Cooling System (RCCS) separate-effects test facility – a facility that aims to provide a high-resolution experimental database to be used to further develop the predictive capabilities of system and CFD codes. We examine the repeatability and reproducibility of the mean velocity and Reynolds stresses for the experiment of six rectangular jets with jet Reynolds numbers of 1.38×104. Furthermore, we discuss the convergence of the mean velocity and Reynolds stresses and some discrepancies observed between separate measurements. By conducting a few PIV measurements to verify the repeatability and reproducibility of the data, we gained insight into how much variation is present between separate measurements – an important quantity that should be included when providing uncertainty bands for PIV data.