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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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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.
Michael Schuller, Theodore A. Parish
Fusion Science and Technology | Volume 8 | Number 2 | September 1985 | Pages 2127-2132
Blanket and Process Engineering | Proceedings of the Second National Topical Meeting on Tritium Technology in Fission, Fusion and Isotopic Applications (Dayton, Ohio, April 30 to May 2, 1985) | doi.org/10.13182/FST85-A24598
Articles are hosted by Taylor and Francis Online.
An aqueous slurry of heavy water and lithium containing solids was examined to assess its merits as the tritium breeding, neutron attenuating, and heat removing portion of a first generation D-T fusion reactor. The results of experimentation and a related computer study are reported here. The numerical and experimental work done indicates a heavy water slurry can breed and retain within the solid particles sufficient tritium to fuel a D-T reactor. Experimental results reported here indicate that the LiF will retain tritium for a period of several days at room temperature. Tritium recoil losses were up to 30% higher than predicted. Tritium release rates from the heated solids were low up to 525°C, but increased rapidly above that temperature.