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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.
Johannes Wolters, Manfred Nickel
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 369-375
Technical Paper | Reactor | doi.org/10.13182/NT77-A31801
Articles are hosted by Taylor and Francis Online.
Certain fuel element positions of the FRJ-2 research reactor at the Nuclear Research Center, Jülich, exhibited violent flow-rate fluctuations. These were caused by periodic vortices that were formed directly below the inlets of the nozzle seats in the core grid plate at the positions in question. The shallow plenum and multiple inlet pipes through which the water is fed to the plenum were identified as the causes of the vortex formation. To eliminate the vortex formation, flow splitters of a “star”-shaped section were installed in the grid plate nozzles. In this manner, it was possible to prevent the fluctuations and utilize the available flow margin for an increased reactor output.