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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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
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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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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.
W. Hage, D. M. Cifarelli
Nuclear Science and Engineering | Volume 112 | Number 2 | October 1992 | Pages 136-158
Technical Paper | doi.org/10.13182/NSE92-A28410
Articles are hosted by Taylor and Francis Online.
A mathematical model is derived for the factorial moments of the probability distribution of neutron signal multiplets within signal-triggered inspection intervals, detected with a paralyzing neutron dead-time counter. These moments are a function of the spontaneous fission rate, the (α ,n) reaction rate, the probability that a neutron generates an induced fission, the neutron detection probability, the dead time, and the nuclear physics data. Monte Carlo calculations are used to check the derived algorithms and the iterative procedure. This procedure is then applied to real measurement data of a PuO2 sample to obtain the correlated multiplets from the numerical values of the factorial moments.
