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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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
The RAIN scale: A good intention that falls short
Radiation protection specialists agree that clear communication of radiation risks remains a vexing challenge that cannot be solved solely by finding new ways to convey technical information.
Earlier this year, an article in Nuclear News described a new radiation risk communication tool, known as the Radiation Index, or, RAIN (“Let it RAIN: A new approach to radiation communication,” NN, Jan. 2025, p. 36). The authors of the article created the RAIN scale to improve radiation risk communication to the general public who are not well-versed in important aspects of radiation exposures, including radiation dose quantities, units, and values; associated health consequences; and the benefits derived from radiation exposures.
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.
