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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
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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.
Dwight W. Underhill
Nuclear Science and Engineering | Volume 63 | Number 2 | June 1977 | Pages 133-142
Technical Paper | doi.org/10.13182/NSE77-A27016
Articles are hosted by Taylor and Francis Online.
Measurements of the release of fission gases from spilled charcoal were made by means of a laboratory scale model developed for this study. It is shown that there is an appreciable retention of fission gases in charcoal and that the release rate can be determined from diffusion theory. For example, from a 1-ft-thick layer of spilled charcoal, it was found that 4.5% of the xenon and 21% of the krypton would be released after 6 h, and that 6.6 and 29%, respectively, would be released after 12 h. These results are in close agreement with the mathematical model developed for the analysis of these experiments. Similar release rates were found for spilled charcoal initially chilled to 0°F. These release rates are conservative because the effect of radioactive decay was neglected, and for this reason a theory was developed that includes the effect of radioactive decay within the spilled charcoal. The combined effects of a slow release rate and radiodecay will serve to mitigate the radiological consequences of a charcoal spill accident.