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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
M. Cumo, G. E. Farello, J. Gasiorowski, G. Iovino, A. Naviglio
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 337-346
Technical Paper | Reactor | doi.org/10.13182/NT80-A17682
Articles are hosted by Taylor and Francis Online.
Two-phase cross flows have received minor consideration in thermal-hydraulics research, notwithstanding their applications in chemical engineering systems. Many types of heat exchangers and steam generators have, at least in a segment of the flow path, a cross direction of a two-phase mixture to a tube bank even in nuclear plant components. The departure from nucleate boiling (DNB), or the dry-out threshold, is one of the main limits that characterize the whole flow field. For this reason it has been deemed interesting to investigate the influence of quality on DNB heat flux in flow boiling, employing a 9-tube bundle with cross flow of Freon 12. Rather surprisingly, the DNB heat flux rises with quality. The rise has been tested from the pool boiling DNB value as predicted by Lienhard up to a saturation value 20% higher. The law of increase may be reasonably well predicted following the well-known critical heat flux theory of Zuber.