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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
Douglas C. Hunt, Deanne Dickinson
Nuclear Technology | Volume 30 | Number 2 | August 1976 | Pages 190-214
Technical Paper | Criticality Array Data and Calculational Method / Chemical Processing | doi.org/10.13182/NT76-A31615
Articles are hosted by Taylor and Francis Online.
The , albedo, interaction potential, weighted interaction Oak Ridge Gaseous Diffusion Plant solid-angle, s/v surface density, fraction critical surface density, and equilateral hyperbola methods are compared by attempting to apply them to 14 different example arrays. The example arrays are distinguished by the type of fissile material in the array units and by the number of units in each array. Arrays with units of Pu(95) metal, U(93) metal, damp U(93)O2, dry Pu(95)O2, U(93)O2(NO3)2 solution, Pu(95)(NO3)4 solution, or U(5)O2F2 solution are considered. It is concluded that if the user has access to a Monte Carlo code such as KENO, he is better off using it than any of the other models for criticality evaluations of specific problems. The remainder of the models are most useful in establishing possible designs for a fissile storage or processing facility. The albedo method is found to be the preferred solid-angle technique, while the s/v surface density method and the method are the most comprehensive and useful of the semiempirical techniques. The s/v method is easier to apply and covers more possible contingencies (e.g., array flooding or persons in arrays), while the method is more difficult to use but has added flexibility, broader applicability, and yields more analytical scaling relations between array parameters.