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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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Denver, CO|The Westin Denver Downtown
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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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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.
Yassin A. Hassan, Wael A. Ibrahim
Nuclear Technology | Volume 119 | Number 1 | July 1997 | Pages 11-28
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT77-A35391
Articles are hosted by Taylor and Francis Online.
Turbulent flow is characterized by random fluctuations in the fluid velocity and by intense mixing of the fluid. A wide range of eddies exists in the flow field. Because these eddies carry mass, momentum, and energy, this enhanced mixing can sometimes lead to serious problems, such as tube vibrations in many engineering systems that include fluid-tube bundle combinations. Nuclear fuel bundles and pressurized water reactor (PWR) steam generators are existing examples of fluid-tube bundle combinations in nuclear power plants. One of the critical areas in PWR steam generators is the weld between the tubes and the tube plate. Fluid-induced vibration problems are often discovered during the operation of such systems because some of the fluid-tube interaction characteristics are not fully understood. Large-eddy simulation, incorporated in three-dimensional computer codes, became one of the promising techniques to estimate flow turbulence. An investigation of the complex flow turbulence in tube bundles was carried out. Simulation of flow across tube bundles with various pitch-to-diameter ratios was performed. Power spectral densities of drag and lift coefficients were used for comparison with experimental data. Estimation of flow-length scales and other important turbulence-related parameters were obtained. Finally, important characteristics of the turbulent flow field were presented with the aid offlow visualization, using both vector and vorticity plots and the flow paths of flow tracers embedded in the flow field.