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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.
F. Capone, J. P. Hiernaut, M. Martellenghi, C. Ronchi
Nuclear Science and Engineering | Volume 124 | Number 3 | November 1996 | Pages 436-454
Technical Paper | doi.org/10.13182/NSE96-A17922
Articles are hosted by Taylor and Francis Online.
Irradiated light water reactor fuel from the BR3 reactor was thermally annealed up to 2500 K in a Knudsen cell, and the effusing vapors were measured by mass spectrometry. The experiments provide data on the stoichiometry evolution of the fuel during release as well as a reliable method to evaluate the diffusion coefficients of volatile and less-volatile fission products.The analysis of the data starts from diffusion of xenon, which clearly shows three typical release stages respectively controlled by radiation damage annealing, self-diffusion, and matrix vaporization. The experimental measurements are also in agreement with the predictions of intragranular trapping models.Barium and cesium showed faster release than xenon, the former being likely to diffuse atomically to the grain boundaries where no evidence of formation of stable zirconates was found. These results were compared with those obtained by a burnup-simulated fuel, where barium was initially present in a perovskite phase, producing essentially different release patterns.