ICONE19-43692 THERMALHYDRAULIC ANALYSIS of 43-, 54-, and 64-ELEMENT BUNDLES WITH UO_2 plus SiC FUEL FOR SUPERCRITICAL WATER-COOLED REACTORS

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SuperCritical Water-cooled Reactors (SCWRs) are one of the six nuclear reactor concepts being developed in the Generation-IV International forum (GIF). The development of SCWRs will increase the thermal efficiency of Nuclear Power Plants (NPPs) to 45-50% as opposed to approximately 30-34% efficiency of the current NPPs. This increase in efficiency is a result of operating at high temperatures of 350℃-625℃ and a pressure of 25 MPa. The current fuel bundle proposed for use in pressure-channel SCWR concepts is the Varient-20 bundle containing 43-elements. Studies have shown that when the 43-element fuel bundle was examined, the fuel centerline temprature might exceed the industry accepted limit of 1850℃ for the UO_2 fuel. The objective of this paper is to examine the use of a higher thermal conductivity fuel such as UO2+SiC in the variant-20 (43-element) , and the newly developed 54- and 64-element bundles. Four different Axial Heat Flux Profiles (AHFPs) are examined for the 43-, 54- and the 64-element bundles. Results of this analysis indicate that the use of UO_2+SiC fuel in the proposed fuel bundles show a significant decrease in the fuel centerline temperature compared to the conventional 43-element bundle design using UO_2 fuel.

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