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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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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.
Richard B. Stout, Alan H. Robinson
Nuclear Technology | Volume 20 | Number 2 | November 1973 | Pages 86-102
Technical Paper | Fuel Cycle | doi.org/10.13182/NT73-A31344
Articles are hosted by Taylor and Francis Online.
An iterative approach was adopted as the most practical method to search for an optimum fuel loading pattern in pressurized water reactors. A minimum peak-to-average power ratio was chosen as the objective characteristic of the optimum loading. A computer program SHUFLE employs a set of logical shuffling statements which utilizes the radial power shape and reactivity positioning of each iteration to predict a shuffle for the succeeding iteration. Independent logic is employed for different sections of the core and for fuel of relatively high and low reactivity. A two-dimensional simulated two-group coarse-mesh diffusion theory model is utilized to calculate the two-dimensional power distribution after each shuffle. The shuffling logic employed in SHUFLE was demonstrated adequate to predict acceptable loading patterns for initial, equilibrium, and nonequilibrium pressurized water reactor cores.