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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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ANS joins others in seeking to discuss SNF/HLW impasse
The American Nuclear Society joined seven other organizations to send a letter to Energy Secretary Christopher Wright on July 8, asking to meet with him to discuss “the restoration of a highly functioning program to meet DOE’s legal responsibility to manage and dispose of the nation’s commercial and legacy defense spent nuclear fuel (SNF) and high-level radioactive waste (HLW).”
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.