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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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.
J. Miida, N. Suda
Nuclear Science and Engineering | Volume 11 | Number 1 | September 1961 | Pages 55-60
Technical Paper | doi.org/10.13182/NSE61-A25984
Articles are hosted by Taylor and Francis Online.
The stability criteria are derived for a nuclear reactor with a power coefficient feedback. The power coefficient feedback is assumed to consist of two feedback paths, each with a single time constant. In reality, the system of the nuclear reactor is often well approximated by this model. The criteria are given in Table I and in Fig. 5, by which one can quickly determine the stability, when parameters are known. They also give an insight into the effects of various parameters on the stability of the nuclear reactor. The application of the criteria to a British-type gas-cooled reactor with a positive temperature coefficient of moderator is demonstrated. Comparisons are made with other works, of different approaches, on a fast reactor and a water-cooled reactor.