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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Candidates announced for 2025 ANS leadership positions
As the U.S. election season finally comes to an end, the annual American Nuclear Society election season is right around the corner. Seventeen candidates have been nominated for the positions of ANS vice president/president-elect, treasurer, and six positions on the board of directors (four U.S. directors, one non-U.S. director, and one student director). Ballots will be sent via email on Tuesday, March 4, 2025, and must be submitted by 1:00 p.m. (EDT) on Tuesday, April 15, 2025.
M. Cumo, G. E. Farello, J. Gasiorowski, G. Iovino, A. Naviglio
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 337-346
Technical Paper | Reactor | doi.org/10.13182/NT80-A17682
Articles are hosted by Taylor and Francis Online.
Two-phase cross flows have received minor consideration in thermal-hydraulics research, notwithstanding their applications in chemical engineering systems. Many types of heat exchangers and steam generators have, at least in a segment of the flow path, a cross direction of a two-phase mixture to a tube bank even in nuclear plant components. The departure from nucleate boiling (DNB), or the dry-out threshold, is one of the main limits that characterize the whole flow field. For this reason it has been deemed interesting to investigate the influence of quality on DNB heat flux in flow boiling, employing a 9-tube bundle with cross flow of Freon 12. Rather surprisingly, the DNB heat flux rises with quality. The rise has been tested from the pool boiling DNB value as predicted by Lienhard up to a saturation value 20% higher. The law of increase may be reasonably well predicted following the well-known critical heat flux theory of Zuber.