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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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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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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.
B. Kim, M. L. Corradini
Nuclear Science and Engineering | Volume 98 | Number 1 | January 1988 | Pages 16-28
Technical Paper | doi.org/10.13182/NSE88-A23522
Articles are hosted by Taylor and Francis Online.
A model for small-scale single droplet fuel/coolant interactions (FCIs) is proposed, which considers the growth of a coolant vapor/liquid interfacial disturbance into a coolant liquid jet during the collapse of the vapor film surrounding the fuel. This results in the encapsulation of the jet as coolant drops beneath the fuel surface and leads to fragmentation of the fuel. In this model, the FCI process is divided into four stages: film boiling around a molten fuel droplet in an infinite coolant pool, film collapse and coolant jet formation, coolant jet penetration and entrapment in the fuel, and rapid evaporation of entrained coolant and fragmentation of the fuel. The process repeats itself cyclically from the second stage. For the single-droplet experiments performed previously, the model predicts the qualitative trends of steam bubble growth and collapse, the final size of fuel fragments, and time scale for the fuel fragmentation.