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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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
Ariz. governor vetoes “fast track” bill for nuclear
Gov. Katie Hobbs put the brakes on legislation that would have eliminated some of Arizona’s regulations and oversight of small modular reactors, technology that is largely under consideration by data centers and heavy industrial power users.
Kuldip Singh, C. C. St. Pierre
Nuclear Science and Engineering | Volume 50 | Number 4 | April 1973 | Pages 382-387
Technical Note | doi.org/10.13182/NSE73-A26573
Articles are hosted by Taylor and Francis Online.
Turbulent mixing rates between adjacent subchannels were obtained at 50 psia for annular flow of air-water mixtures in a simulated square-square rod bundle geometrical array using a tracer technique. The gap spacing was varied by a factor of 5. Mixing rates were found to be flow regime dependent, decreasing exponentially with subchannel mass flux and quality and increasing with gap spacing. Enhanced liquid interchange was measured in the low quality bubble flow regime and high quality annular flow regime. The results presented here are in qualitative agreement with data obtained by other investigators using steam-water at elevated pressures.