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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Excelsior University student section awarded community education grant
The American Nuclear Society Student Section at Excelsior University in Albany, N.Y., was awarded a $5,000 grant from the ANS Student Section Strategic Fund initiative for its program, Empowering Tomorrow’s Nuclear Innovators: A Collaborative Approach to Nuclear Technology Education and Awareness.
Michael S. Gorman, Marilyn Delgado, Saya Lee, Yassin A. Hassan
Nuclear Technology | Volume 205 | Number 7 | July 2019 | Pages 881-890
Technical Paper – Selected papers from the 2018 ANS Student Conference | doi.org/10.1080/00295450.2019.1600998
Articles are hosted by Taylor and Francis Online.
A model helical coil steam generator test section was designed and constructed to visualize the flow between two adjacent tube bundles—inner and outer bundle—that coil in opposite directions to one another. This study focuses on visualizing and characterizing fluid properties on the shell side of the unique tube-and-shell heat exchanger design. Flow within the shell side is characterized by recirculation regions below the tubes, or wake regions, and streamlined flow between tube bundles. The matched refractive index particle image velocimetry (PIV) experimental technique was used to experimentally capture the flow between the adjacent tube bundles. Images for PIV analysis were taken at three cross-sectional planes of the test section at 10 000 frames per second of an area approximately 24.54 23.20 mm. Average vertical and transverse velocity components were analyzed at a distance of r/rr = 1.1 about the tube centers at a specific rod height to observe flow separation and flow characteristics between the tube bundles. Measurements showed the magnitude of the normalized vertical velocity increased through the planes as the flow followed the helical pitch of the tube bundles. The flow was also observed to experience significant flow separation from recirculating eddies and vortex shedding across the rods.