ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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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Nuclear Science and Engineering
January 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Francisco I. Valentín, Narbeh Artoun, Ryan Anderson, Masahiro Kawaji, Donald M. McEligot
Nuclear Technology | Volume 196 | Number 3 | December 2016 | Pages 661-673
Technical Paper | doi.org/10.13182/NT16-46
Articles are hosted by Taylor and Francis Online.
Very high temperature reactors (VHTRs) with helium-cooled prismatic cores are one type of Generation IV gas-cooled reactors proposed for implementation in next-generation nuclear power plants. To contribute to the VHTR development, a high-temperature/high-pressure test facility has been constructed and used to investigate the convection heat transfer of gaseous coolants. This test facility consisted of a single flow channel with a diameter of 16.8 mm in a graphite column with a length of 2.7 m (9 ft) equipped with four 2.3-kW heaters. Convection heat transfer experiments were conducted with air, nitrogen, and helium for inlet Reynolds number (Re) values ranging from 500 to 70000. Extensive three-dimensional numerical modeling was also performed using a commercial finite element package, COMSOL Multiphysics. The numerical results agreed with the convection heat transfer data, with maximum error percentages under 15%. Based on this agreement, important information was extracted from the numerical model regarding the axial and radial velocity and temperature profiles as well as the axial variations in gas properties. This work examines deteriorated turbulent heat transfer and flow laminarization for a wide range of Re, including laminar, transition, and turbulent flows.