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Division Spotlight
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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
NWMO to select Canadian repository site this year
Canada’s Nuclear Waste Management Organization, a not-for-profit organization responsible for the long-term management of the country’s intermediate- and high-level radioactive waste, is set to select a site for a deep geologic repository by the end of the year.
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.