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Research Papers

Temperature Distribution Inside Fresh-Fuel Pins of Pressure-Tube Supercritical-Water-Cooled Reactor

[+] Author and Article Information
Vitali Kovaltchouk

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada
e-mail: vitali.kovaltchouk@uoit.ca

Eleodor Nichita

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada
e-mail: eleodor.nichita@uoit.ca

Eugene Saltanov

Faculty of Energy Systems and Nuclear Science,
University of Ontario Institute of Technology,
2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada
e-mail: eugene.saltanov@uoit.ca

1Corresponding author.

Manuscript received April 14, 2015; final manuscript received July 18, 2015; published online December 9, 2015. Assoc. Editor: Thomas Schulenberg.

ASME J of Nuclear Rad Sci 2(1), 011008 (Dec 09, 2015) (5 pages) Paper No: NERS-15-1057; doi: 10.1115/1.4031163 History: Received April 14, 2015; Accepted July 27, 2015

The radial temperature profile for ThO2-PuO2 fresh-fuel pins of the pressure-tube supercritical-water-cooled reactor (PT-SCWR) is simulated for two different radial distributions of the ThO2 and PuO2, one whereby the ThO2 and PuO2 are mixed together in a single, homogeneous region, and another one whereby ThO2 and PuO2 occupy separate radial regions inside the pin with the ThO2 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.

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Figures

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Fig. 1

Schematic diagram of the Canadian PT-SCWR conceptual design [1]

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Fig. 2

Fuel pin configurations: (a) homogeneous mixture of ThO2 and PuO2; (b) separate regions of ThO2 and PuO2

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Fig. 3

Single-cell DRAGON geometry

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Fig. 4

Power production distribution across the PT-SCWR reactor obtained from neutronics simulation in one-cell approximation. Values are normalized to an average channel linear power of one

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Fig. 5

Simulated power density distributions inside the fuel pins for the inner and outer rings

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Fig. 6

Temperature distributions inside the fuel pins for the homogeneous single-region configuration

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Fig. 7

Temperature distributions inside the two-region fuel pins. The dashed line corresponds to the location of boundary between PuO2 and ThO2 fuel materials

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