Pressure drop calculation and temperature profiles associated with fuel and sheath are important aspects of a nuclear reactor design. The main objective of this paper is to determine the pressure drop in a fuel channel of a SuperCritical Water-cooled Reactor (SCWR) and to calculate the temperature profile of the sheath and the fuel bundles. One-dimensional steady-state thermal-hydraulic analysis was conducted. In this study, the pressure drops due to friction, acceleration, local losses, and gravity were calculated at supercritical conditions.
Pressure Drop Analysis of a Pressure-Channel Type SuperCritical Water-Cooled Reactor
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Dragunov, A, & Peiman, W. "Pressure Drop Analysis of a Pressure-Channel Type SuperCritical Water-Cooled Reactor." Proceedings of the ASME 2013 International Mechanical Engineering Congress and Exposition. Volume 15: Safety, Reliability and Risk; Virtual Podium (Posters). San Diego, California, USA. November 15–21, 2013. V015T16A017. ASME. https://doi.org/10.1115/IMECE2013-67383
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