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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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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.
P. R. McClure, M. T. Leonard, A. Razani
Nuclear Science and Engineering | Volume 114 | Number 2 | June 1993 | Pages 102-111
Technical Paper | doi.org/10.13182/NSE93-A24021
Articles are hosted by Taylor and Francis Online.
A computational model is described for fission product release from molten pools of uranium-aluminum (U-Al) metal. Liquid-metal pools may form during severe accidents in U-Al-fueled reactors if multiple core assemblies melt and relocate to the bottom of the reactor vessel. At present, data for the release of fission products from intact U-Al fuel are sparse, and no data are available for the release of fission products from U-Al in the form of molten pools. This investigation postulates three phenomena that govern fission product release from such a system: (a) Rayleigh cell convection in the molten pool; (b) nucleation of volatile radionuclide species with concomitant bubble dynamics; and (c) diffusion from the pool surface. Selected sensitivity analyses have been performed to study the dependence of model predictions on uncertain input parameters and thus to characterize critical needs for experimental data. The results of the sensitivity analysis indicate that parameters that characterize the nucleation rate of volatile species in the pool have the greatest effect on the calculated rate of fission product release.