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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
J. C. Carter, D. W. Sparks, J. H. Tesster
Nuclear Science and Engineering | Volume 8 | Number 4 | October 1960 | Pages 326-339
Technical Paper | doi.org/10.13182/NSE60-A28863
Articles are hosted by Taylor and Francis Online.
This article is concerned with what are considered to be the significant feedback mechanisms of EBR-I Mark III. The objective is that of providing an explanation of the dynamic behavior of this particular fast reactor. A mathematical model of the core and blankets is postulated and an analog of the equations is constructed. The response of the model and of the reactor to the same signal at any given operating conditions are in good agreement. The analog facilitates an analysis of the feedback producing the response. The reactor is considered to constitute a closed loop nonlinear mechanical system with forcing functions resulting from variations in neutron density and the flow of NaK through the core and blankets. The significant sources of internal feedback are considered to be the variation in volume of the uranium and the variation in the density of NaK. Resistance to the free motion of uranium in response to thermal expansion provides the significant nonlinearities in the system. This resistance results from the physical characteristics of the redundant structure constituting the core, blankets, and containing shell. All the equations defining the time dependent physical phenomena are developed from an analysis of the reactor system, but the constants in the nonlinear equations of motion of the materials of the core and blankets are synthesized from low power operation of the reactor.