The radial temperature profile for fresh-fuel pins of the pressure-tube supercritical-water-cooled reactor (PT-SCWR) is simulated for two different radial distributions of the and , one whereby the and are mixed together in a single, homogeneous region, and another one whereby and occupy separate radial regions inside the pin with the occupying the inner region. The radial power density in each fuel pin is calculated from a lattice-level transport calculation using the lattice code DRAGON and is used together with the temperature-dependent fuel thermal conductivity to analytically solve the heat conduction equation and thus calculate the temperature profile inside the fuel pin. Results indicate that, for fresh fuel, the centerline temperature is much lower for a two-region pin than for a single-region pin, and thus, the risk of fuel melting is greatly reduced for the two-region fuel compared to the single-region fuel.
Temperature Distribution Inside Fresh-Fuel Pins of Pressure-Tube Supercritical-Water-Cooled Reactor
Manuscript received April 14, 2015; final manuscript received July 18, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.
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Kovaltchouk, V., Nichita, E., and Saltanov, E. (December 9, 2015). "Temperature Distribution Inside Fresh-Fuel Pins of Pressure-Tube Supercritical-Water-Cooled Reactor." ASME. ASME J of Nuclear Rad Sci. January 2016; 2(1): 011008. https://doi.org/10.1115/1.4031163
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