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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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.
F. C. Engel, R. A. Markley, A. A. Bishop
Nuclear Science and Engineering | Volume 69 | Number 2 | February 1979 | Pages 290-296
Technical Paper | doi.org/10.13182/NSE79-A20618
Articles are hosted by Taylor and Francis Online.
Laminar, transition, and turbulent parallel flow pressure drop across wire-wrapped hexagonal rod bundles positioned inside a duct were determined in tests using water, sodium, and air. A smooth transition region from turbulent to laminar flow that occurred over the Reynolds number range from 5000 to 400 characterized the resulting friction factor behavior. The continuous transition region could be explained in terms of the fraction of the flow area in turbulent flow. Laminar friction factors calculated from individual subchannel measurements could be correlated by the same expression found for rod-bundle-averaged conditions. In the laminar range, the friction factor was correlated by the expression f = 110/Re, in the turbulent range by f = 0.55/Re0,25, and in the transition range by where is the intermittency factor. A general laminar flow friction factor correlation was developed: This correlation agrees satisfactorily with limited laminar flow data from rod bundles having different wire-wrap lead pitch-to-diameter ratios.