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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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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.
Robert A. Anderl, Robert J. Pawelko, Galen R. Smolik, Richard G. Castro
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 738-744
Safety and Environment | doi.org/10.13182/FST98-A11963702
Articles are hosted by Taylor and Francis Online.
This paper presents the results of experiments and analyses to quantify the chemical reactivity of plasma-sprayed (PS) Be specimens exposed to steam. Test specimens with densities of 94% theoretical density (TD) and 92% TD were prepared by a low-pressure-plasma-spraying (LPPS) technique. Sample density, porosity and specific surface area were measured using immersion density and gas-adsorption techniques. Microstructural characterization was done using optical and electron microscopy. Hydrogen generation rates were obtained from tests of specimens in steam at temperatures from 350 to 1000°C. Below 700°C, hydrogen generation rates for the 94% TD material were somewhat higher than rates for 100% TD Be, but they were substantially lower than rates for the 92% TD Be and for previously tested PS-Be and porous Be. Reaction rate differences correlated with specific surface area differences for the materials tested.
