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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.
J. P. Foster, A. Boltax
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 181-188
Technical Paper | Material | doi.org/10.13182/NT80-A32421
Articles are hosted by Taylor and Francis Online.
Large swelling values associated with a gradual temperature reduction during irradiation have been observed for pressurized tubes irradiated at two initial irradiation temperatures. A comparison of the pressurized tube data with WSA-4 fuel pin cladding swelling data shows that the same behavior is observed in fuel pins subject to temperature changes during irradiation. The fuel pin data cover a large temperature interval, and this information was used to determine temperature and fluence dependencies of the observed enhanced swelling effect. The results show that the enhanced swelling with temperature reductions depends on the initial irradiation temperature, with the maximum value occurring at ∼500°C. The data indicate that the effect saturates with fluence.