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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Become a knowledge manager at UWC 2024
The American Nuclear Society is now accepting applications for knowledge managers to work during the 2024 Utility Working Conference and Vendor Technology Expo. This year’s UWC, “Nuclear Momentum: Advancing Our Clean Energy Future,” will be held August 4–7, 2024, at the JW Marriott Marco Island Beach Resort on Marco Island, Fla.=
Pablo E. Araya, Miles Greiner
Nuclear Technology | Volume 167 | Number 3 | September 2009 | Pages 384-394
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT09-A9078
Articles are hosted by Taylor and Francis Online.
Experiments performed by Lovett (1991) measured the temperature of an 8 × 8 array of horizontal heated rods in air within a constant temperature enclosure. That apparatus was a scaled-down model of a spent boiling water reactor fuel assembly in a transport package. In the current work, three-dimensional computational fluid dynamics simulations of natural convection and radiation heat transfer within this domain were conducted to determine appropriate boundary conditions and benchmark the results. Initial simulations employed nearly equal specified temperatures on the walls and endplates, and insulated rod ends. They accurately reproduced the shapes of the temperature profiles in the midplane but overpredicted the temperature level at the highest heat load. Simulations that included conduction within the endplates and convection from their outside surfaces more accurately modeled heat losses and brought the midplane temperatures close to the measured data. These experiences will be used to design experiments to benchmark simulations of spent fuel assemblies in transport package support structures.