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Division Spotlight
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.
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.