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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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Fusion Science and Technology
May 2025
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.
Yong Hu, H. G. Yang, W. W. Zhao, Q. Zhan, X. M. Yuan, TMT Team
Fusion Science and Technology | Volume 60 | Number 4 | November 2011 | Pages 1531-1534
Interaction with Materials | Proceedings of the Ninth International Conference on Tritium Science and Technology (Part 2) | doi.org/10.13182/FST11-A12724
Articles are hosted by Taylor and Francis Online.
Experiments on deuterium permeation through S.S.316L with FeAl/Al2O3 composite coating have been performed in the temperature range 277-600°C at driving pressures 1-50kPa. As comparison, the tests for samples with natural oxidation film and Ni-plating have also been performed. The apparent deuterium permeability in the sample with FeAl/Al2O3 coating is an order of magnitude lower than that with natural oxide layer, and is at least three orders of magnitude lower than that in the non-oxidized material by inference. The apparent activation energy of deuterium permeation is 76.6kJ/mol for the coated sample and 61.3kJ/mol for the sample with natural oxidation film. The exponential dependences of steady flux for the samples on the pressure are 0.89 for FeAl/Al2O3 coating, 0.65 for natural oxidation film, and 0.55 for Ni-plating, that reflects different permeation mechanism for various surfaces. In addition, the trapping effect of defects on hydrogen isotope was inferred according to the different characteristic of permeation flux curves for various samples.
