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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.
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
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
John T. Mihalczo
Nuclear Science and Engineering | Volume 27 | Number 3 | March 1967 | Pages 557-563
Technical Paper | doi.org/10.13182/NSE86-A17621
Articles are hosted by Taylor and Francis Online.
A method is described for predicting the neutron multiplication factors of geometrically complicated configurations of unreflected unmoderated enriched- uranium metal from the results of two delayed-critical experiments in simple geometry. The method requires two constants characteristic of the metal. These are the total collision cross section (∑t) and the number of neutrons produced per collision (υ∑f/∑t), which are obtained from the two experiments by using S12 transport-theory calculations with isotropic scattering. These constants, together with the assumption of isotropic scattering, are then used in 05R Monte Carlo neutron-transport calculations to predict the multiplication factors. The method has been tested by predicting the multiplication factors of 21 different delayed-critical assemblies with a wide variety of geometries to within a standard deviation of 1.5%.