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). 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. The total pressure drop due to all these parameters was between 108 and 121 kPa.
- Nuclear Engineering Division
Pressure Drop Analysis of a Re-Entrant Fuel Channel in a Pressure-Channel Type SuperCritical Water-Cooled Reactor
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Maghsoudi, S, Peiman, W, Pioro, I, & Gabriel, K. "Pressure Drop Analysis of a Re-Entrant Fuel Channel in a Pressure-Channel Type SuperCritical Water-Cooled Reactor." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition. Prague, Czech Republic. July 7–11, 2014. V005T17A045. ASME. https://doi.org/10.1115/ICONE22-30616
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