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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2005.1
- 수록면
- 363 - 374 (12page)
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A heterogeneous thorium-based Kyung Hee Thorium Fuel (KTF) assembly design was assessed for application in the
APR-1400 to study the feasibility of using thorium fuel in a conventional pressurized water reactor (PWR). Thermal hydraulic
safety was examined for the thorium-based APR-1400 core, focusing on the Departure from Nucleate Boiling Ratio (DNBR)
and Large Break Loss of Coolant Accident (LBLOCA) analysis. To satisfy the minimum DNBR (MDNBR) safety limit
condition, MDNBR>1.3, a new grid design was adopted, that enabled grids in the seed and blanket assemblies to have different
loss coefficients to the coolant flow. The fuel radius of the blanket was enlarged to increase the mass flow rate in the seed
channel. Under transient conditions, the MDNBR values for the Beginning of Cycle (BOC), Middle of Cycle (MOC), and
End of Cycle (EOC) were 1.367, 1.465, and 1.554, respectively, despite the high power tilt across the seed and blanket.
Anticipated transient for the DNBR analysis were simulated at conditions of 112% over-power, 95% flow rate, and 2 C
higher inlet temperature. The maximum peak cladding temperature (PCT) was 1,173K for the severe accident condition of
the LBLOCA, while the limit condition was 1,477K. The proliferation resistance potential of the thorium-based core was
found to be much higher than that of the conventional UO2 fuel core, 25% larger in Bare Critical Mass (BCM), 60% larger in
Spontaneous Neutron Source (SNS), and 155% larger in Thermal Generation (TG) rate; however, the radio-toxicity of the
spent fuel was higher than that of UO2 fuel, making it more environmentally unfriendly due to its high burnup rate.
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