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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.
R. G. Hart, M. Lounsbury, R. W. Jones, M. J. F. Notley
Nuclear Science and Engineering | Volume 18 | Number 1 | January 1964 | Pages 6-17
Technical Paper | doi.org/10.13182/NSE64-A18137
Articles are hosted by Taylor and Francis Online.
A study of five methods of determining burnup in fuel test specimens has been made to determine the confidence which can be placed in the burnup numbers so obtained. The five methods compared are (1) uranium-235 depletion, (2) cobalt monitoring, (3) cesium-137 production, (4) plutonium production, and (5) calorimetry. The study includes a comparison of data obtained on portions of the specimen with that obtained on the complete specimen. It has been found that all of the methods give burnup values that are within ± 5% of the “best” burnup value, the “best” value being defined as the unweighted average of all the available results on a particular sample. The limitations and pitfalls of all the methods are discussed in some detail. It has further been found that a complete cross-section of the test specimen, approximately ½in. long, is sufficient sample to give representative burnup data. The integration from this to the complete specimen is relatively straightforward. Any sample not comprising a complete cross-section involves radial as well as longitudinal integration, giving results that are relatively uncertain, particularly in samples of high heat rating where migration of some species is a distinct possibility.