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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Wyoming OKs construction of TerraPower’s Natrium plant
Progress continues for TerraPower’s Natrium plant, with the latest win coming in the form of a state permit for construction of nonnuclear portions of the advanced reactor.
Edward L. H. Tang
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 65-75
Technical Paper | doi.org/10.13182/NSE79-A21286
Articles are hosted by Taylor and Francis Online.
The rod-drop experiment has been studied for the purpose of predicting reactor resonance power level. A simplified model, referred to here as the “collective model,” is introduced for experimental analysis of the rod-drop transient response. The mathematical description of this model is formulated by describing the experimentally observed oscillatory response by an overall damping factor and an overall oscillatory frequency. Based on this model, it is found that the overall damping factor is approximately a linear function of the reactor power. Accordingly, we propose an experimental procedure, the method of least-squares approach, which provides an exponential approach to the resonance power level as a function of the number of rod drops. It is shown that the accuracy of measurement in the rod-drop experiment greatly affects this technique for core dynamic analysis. The present results show that for an experiment of negligible experimental error, only two or three rod drops are needed to predict the resonance power level up to an accuracy of 0.2%, while for an experiment of ±5% in error, it requires four to five rod drops to reach an accuracy of 0.8%.