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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.
S. Barabaschi, A. Pulacci
Nuclear Science and Engineering | Volume 12 | Number 2 | February 1962 | Pages 160-168
Technical Paper | doi.org/10.13182/NSE62-A26054
Articles are hosted by Taylor and Francis Online.
The paper describes the control system of the Ispra-1 reactor which has been designed and built by the Servomechanism and Reactor Control Laboratory of the CNEN. The system adopted follows the two channel philosophy, in order to keep to a minimum the stresses of the regulating rod, even when the reactor is very noisy and when high precision in the regulating of the power level is required. The stability of the regulating system during constant power operation and during the constant period transient is analyzed. Results of testing of the real system on a nuclear reactor simulator are reported.