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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.
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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
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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.
Matthias Vanderhaegen, Alix Le Belguet
Nuclear Science and Engineering | Volume 176 | Number 2 | February 2014 | Pages 115-137
Technical Paper | doi.org/10.13182/NSE12-99
Articles are hosted by Taylor and Francis Online.
Sodium boiling phenomena in nuclear reactors have been reviewed in the context of the renewed interest in sodium-cooled fast reactors. This paper presents all properties that influence sodium boiling behavior, including thermodynamic and transport properties, as well as the typical composition of reactor-grade sodium, the surface wetting, radiative heat transfer properties, and noncondensable behavior. Starting from these properties, the tendency for high superheat is explained, together with the reasons that the problem of superheat can be neglected for reactor systems. The peculiar boiling behavior of sodium in assemblies is explained on the basis of the temperature profile. This leads us to conclude that a typical slug flow pattern prevails for sodium boiling. The boiling heat transfer for pool film boiling is also given, deducing that the critical heat flux phenomena for sodium boiling in reactor systems is mainly related to dryout and not to the departure from nucleate boiling. The correlations that exist for the minimum film-boiling temperature are discussed in light of their applicability to liquid sodium. Although there are already a large amount of data, gaps in the current understanding of sodium are highlighted.