ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Hasna J. Khan, George Kosaly
Nuclear Technology | Volume 75 | Number 1 | October 1986 | Pages 34-45
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A15975
Articles are hosted by Taylor and Francis Online.
Void fraction calculations have been performed using the subchannel drift-flux code CANAL. Using void and flow distributions in rod bundle geometry, a value of C0 has been estimated for bundle-averaged void fraction calculation in one-dimensional approximations. Successful prediction of the average void fraction is observed for the annular rod bundle geometry of the FRIGG experiment. In order to perform subchannel void fraction calculation, a C0 model has been developed for one-dimensional subchannel geometry. The implicit form of the C0 model developed accounts for void and flow conditions in the adjacent subchannels existing at the common interfaces, i.e., at the gap spacing between the subchannels. It appears that the magnitude of C0 varies between subchannels (annular rings of FRIGG geometry) but remains almost constant within each subchannel. Good agreement is observed between prediction and data for subchannel void fractions in axially uniform and nonuniform heated rod bundles.