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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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
G. M. Roach, Jr., S. I. Abdel-Khalik, S. M. Ghiaasiaan, M. F. Dowling, S. M. Jeter
Nuclear Science and Engineering | Volume 131 | Number 3 | March 1999 | Pages 411-425
Technical Paper | doi.org/10.13182/NSE99-A2043
Articles are hosted by Taylor and Francis Online.
Critical heat flux (CHF) associated with the flow of subcooled water in heated microchannels is experimentally investigated. Four different channels, all 16 cm in length, are used: two are circular and uniformly heated and have 1.17- and 1.45-mm diameters, and the other two represent flow channels in a microrod bundle with a triangular array and 1.131-mm hydraulic diameter, with one uniformly heated over its entire surface and the other heated only over the surfaces of the surrounding rods. The test section parameter ranges are as follows: 250 to 1000 kg/m2s mass flux, 344- to 1043-kPa exit pressure, 407- to 1204-kPa inlet pressure, and 49 to 72.5°C inlet temperature. The effect of noncondensables (air) on CHF is also examined by repeating some of the experiments with degassed water and with water saturated with air at test section inlet pressure and temperature.Critical heat flux occurs at very high flow qualities (0.36 and higher) in all the tests and indicates the occurrence of dryout. Furthermore, the CHF appears to monotonically increase with increasing mass flux or pressure. The CHF depends on channel cross-section geometry, and unlike high mass flux data, it increases with increasing channel diameter. The dissolved air slightly increases the CHF for the smaller circular channel and reduces the CHF for the other test sections. The experimental data are compared with the predictions of three widely used empirical correlations. The Bowring-1972 correlation could predict the data with reasonable accuracy.