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Division Spotlight
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.
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.
James M. Wu, Chun-Fa Chuang
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 40-49
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33301
Articles are hosted by Taylor and Francis Online.
Three-dimensional natural convection of the compacted spent fuel rod in a pool was studied. A numerical technique was developed based on the conservation of mass, momentum, and energy of a typical flow element in the channel. The coolant flow is laminar and single phase. The decay heat generation from the spent fuel rod was assumed to be a chopped sine curve. Different configurations of the fuel rods were considered. Calculation was done by varying the inlet coolant temperature, decay heat generation, radius of the spent fuel rod, and distance between spent fuel rods. A simple correlation for the Nusselt number, hydraulic diameter, Prandtl number, and Grashof number was obtained.
