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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.
Michael S. Milgram
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 249-269
Technical Paper | doi.org/10.13182/NSE78-A27304
Articles are hosted by Taylor and Francis Online.
The integral transport equation for the flux density in the interior of an infinite homogeneous cylinder is reduced to a matrix eigenvalue problem for the critical cylinder and a set of linear algebraic equations for the driven case with surface in-currents. The matrix elements are identified as moments of modified Bessel functions and are easily computed. A connection is made with classical diffusion theory via a related matrix eigenvalue problem, from which the diffusion coefficient and extrapolation endpoint can be computed. Analytic properties of the matrix elements are used to obtain approximate solutions for (optically) dense and transparent cylinders. Numerical results are given for the American Nuclear Society benchmark black rod problem, and the fact that only small matrices are required for a large range of problems is demonstrated.