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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
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.
R. T. Jacobs, J. A. Merrill
Nuclear Science and Engineering | Volume 8 | Number 6 | December 1960 | Pages 480-496
Technical Paper | doi.org/10.13182/NSE60-A25834
Articles are hosted by Taylor and Francis Online.
The comparative correlations of this report thoroughly demonstrate that significantly more precise equations for calculating burnout heat flux can be obtained by following the proposed “system-describing” concept, that if the independent, system-describing variables of a system are known, the burnout heat flux can be predicted. With this concept, the independent variable of inlet temperature has been used rather than the dependent variable of outlet subcooling or enthalpy. The same statistical (regression analysis) method of correlation was used for burnout data from several sources with both inlet temperature and outlet enthalpy so that the consistently better predictions using inlet temperature would not be attributed to using a different method of correlation. Due to the fact that Reactor technology and design no longer allow the engineer safety factor added upon safety factor, a decided advantage of the regression analysis correlation is that it is possible to calculate the statistical uncertainty of the predicted burnout heat flux.