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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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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.
Guy G. Loomis, Rex W. Shumway
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 151-163
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33310
Articles are hosted by Taylor and Francis Online.
Flow film boiling heat transfer data from Semiscale Mod-3 gravity feed reflood experiments have been compared to existing film boiling correlations. The existing film boiling correlations were found to be inadequate for calculating Semiscale rod bundle results in the low void fraction region. Therefore, a new correlation for flow film boiling was developed. The new correlation is applicable for boiling water with stainless steel electrically heated vertical rods for a pressure range from 127 to 390 kPa. The new correlation is sensitive to such parameters as the local void fraction, the wall temperature, the bulk vapor temperature, and the total mass flux.