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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
M. Fadaee, S. D. Yu
Nuclear Science and Engineering | Volume 188 | Number 1 | October 2017 | Pages 85-101
Technical Paper | doi.org/10.1080/00295639.2017.1337382
Articles are hosted by Taylor and Francis Online.
Unsteady fluid forces acting on CANDU fuel bundles inside a pressure tube are an important source that induces bundle vibration during operation. In this study, a comprehensive three-dimensional computational fluid dynamics (CFD) model is presented to investigate unsteady coolant flow through a 37-element CANDU fuel bundle in a pressure tube. The CFD model includes all fuel elements with endcaps and spacer pads and two endplates. Large eddy simulation is employed to solve the complex CFD model. Time histories and frequency spectra of unsteady fluid forces acting on individual components and the fuel bundle are predicted. Fluid velocities and flow development after the upstream endplate and spacer pads are also investigated. The effects of the spacer pads and endcaps on the mean value and standard deviation of unsteady fluid forces and flow characteristics are predicted.