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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
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.
Dov Ingman, Amos Notea
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 99-104
Technical Paper | Radioisotopes and Isotope | doi.org/10.13182/NT86-A33758
Articles are hosted by Taylor and Francis Online.
The definition of edge is essential for dimension extraction from radiographic testing. One of the straightforward techniques for edge enhancement is the use of the derivative operator. This technique is analyzed for various types of edges on the basis of general definition of the edge. The radiographic response is considered as a convolution of ideal image with a blurring function. The types of edges responding to the technique with sufficient accuracy are found, while in other cases this technique is not recommended. The derivative approach is demonstrated for the localization of edges in a calibrated reactor fuel element tested by neutron radiography. The radiograph is digitized with an automatic microdensitometer, and the limitations of the method are shown for pellet axial and radial edges.