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Division Spotlight
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.
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.
Yue Jin, Faith R. Beek, Fan-Bill Cheung (Penn State), Stephen M. Bajorek, Kirk Tien, Chris L. Hoxie (NRC)
Proceedings | Advances in Thermal Hydraulics 2018 | Orlando, FL, November 11-15, 2018 | Pages 98-108
In the current study, a new mass quality correlation was developed for the dispersed flow film boiling (DFFB) regime in a rod bundle geometry during bottom reflood. The new correlation was based on the fundamental conservation equations such that the physics during the reflood process can be adequately captured. It is found that the actual mass quality as well as the vapor drift velocity in the DFFB regime are functions of the void fraction, interfacial heat transfer, vapor superheat, droplet size, quench front location and the fluid properties. The Rod Bundle Heat Transfer (RBHT) reflood tests were used to verify the validity of the new correlation and to determine the coefficients. It was found that the current model is able to predict the two-phase mass quality well within 10% error when compared to experimental data.