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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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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
David G. Morris, Charles B. Mullins, Graydon L. Yoder, Jr.
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 82-93
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33597
Articles are hosted by Taylor and Francis Online.
Dispersed-flow film boiling data were obtained in a large rod bundle (8 × 8) under steady-state and transient conditions with upward flowing high-pressure, high-temperature water. The bundle is equipped with detailed thermometry, and has geometry typical of later generation pressurized water reactors with 17 × 17 fuel assemblies. Comparisons with the data to empirical correlations commonly used to predict heat transfer in dispersed flow indicate that the Dougall-Rohsenow and Groeneveld-Delorme correlations overpredict and underpredict heat transfer, respectively, while the Groeneveld 5.7 and Condie-Bengston IV correlations perform reasonably well. Spacer grids are shown to cause rod surface temperature depressions of up to 100 K from the upstream to downstream side of the grid. Grid effects persist for 20 to 30 hydraulic diameters downstream of the grid.