ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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May 2025
Latest News
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.
E. D. Hughes, M. P. Paulsen, L. J. Agee
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 410-421
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32787
Articles are hosted by Taylor and Francis Online.
A drift-flux model of two-phase flow has been incorporated into the RETRAN computer program. The drift-flux equations allow more accurate prediction of the void fraction than the homogeneous mixture model equations that form the basic RETRAN two-phase flow model. In addition, the drift-flux model is more physically based than empirical correlations of void fraction. Comparisons of model predictions with experimental data show good agreement for both subcooled and saturated boiling of water.