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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.
THOMAS J. BURNETT
Nuclear Science and Engineering | Volume 2 | Number 3 | May 1957 | Pages 382-393
Technical Paper | doi.org/10.13182/NSE57-A25403
Articles are hosted by Taylor and Francis Online.
The potential hazard resulting from the accidental release of the fission products accumulated in a reactor enters into both design and site selection. This hazard is associated principally with the resultant internal exposure which is greatest from isotopes with long half-lives. A useful index of a reactor's potential hazard is the accumulated number of activity quantities each capable of 25 rem total bone exposure. This hazard index is sensitive to the relative composition of these fission products and is given by the empirical equation: HI = 112.5 P0.37 (Pt)0.63, in which P is the power in watts at which the reactor is operated for t days. This equation, valid over the time range of principal interest (30 to 1000 days), permits comparison of potential hazard for constant burnup (the Pt product) and/or other design parameters.