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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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
S. T. Perkins, E. F. Plechaty, R. J. Howerton
Nuclear Science and Engineering | Volume 90 | Number 1 | May 1985 | Pages 83-98
Technical Paper | doi.org/10.13182/NSE85-A17433
Articles are hosted by Taylor and Francis Online.
Using a Monte Carlo technique and recent double-differential measurements, a reevaluation of the 9Be(n, 2n) reaction has been completed. This evaluation is currently available for use in the most recent evaluation of the Evaluated Nuclear Data Library and will be used in ENDF/B-VI. Calculations have been carried out with these data, and implications for neutron multiplication in beryllium fusion reactor blankets are discussed.
