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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
Jonathan Gérardin, Pierre Ruyer, Pascal Boulet
Nuclear Science and Engineering | Volume 178 | Number 1 | September 2014 | Pages 103-118
Technical Paper | doi.org/10.13182/NSE13-61
Articles are hosted by Taylor and Francis Online.
The reflooding of the reactor core during a loss-of-coolant accident (LOCA) in a pressurized water reactor is a rather complex conjugate heat transfer situation. In the mist flow regime downward from the quench front, the rod wall can reach temperatures up to 1400 K, and radiative heat transfer can play a significant role. The present study concerns the accurate numerical computation of radiative heat transfer throughout a subchannel with LOCA representative flow conditions resolved at a computational fluid dynamics–scale spatial discretization thus allowing the large gradients of two-phase-flow properties to be determined. The accuracy of several methods to solve the radiative transfer equations has been compared both in canonical test cases and in low-pressure LOCA conditions. The role of radiative transfer is obvious in all variables including those related to the dynamics of the flow. Analysis of the gap between the present estimation and a standard correlation has been performed. It leads to the conclusion that radiative transfer can be taken into account accurately by correlation as soon as well-defined radiative properties are considered. The transfer is very sensitive to droplet size and concentration and can be as large as the convective heat transfer.