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Division Spotlight
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.
Meeting Spotlight
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.
Shan Heng Chien, A. R. Wazzan, D. Okrent
Nuclear Technology | Volume 46 | Number 1 | November 1979 | Pages 110-126
Technical Paper | Fuel | doi.org/10.13182/NT79-A32384
Articles are hosted by Taylor and Francis Online.
A simplistic analytical treatment is given of the effects of dislocations and solid fission products on the behavior of fission gas in oxide fuel elements during fast thermal transients. The analysis is coupled with the BUBE code (a code that models equilibrium and nonequilibrium fission gas bubbles in thermal transients) and used to analyze two Transient Reactor Test Facility transients. The results suggest that the effect of dislocations on swelling and fission gas release is negligible, but that the effect of solid fission products is important.
