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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 1,173 - 1,183 (11page)
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초록· 키워드
오류제보하기
Transient fluid velocity and pressure fields in a pressurized water reactor (PWR) steam generator (SG)secondary side during the blowdown period of a feedwater line break (FWLB) accident were numericallysimulated employing the saturated water flashing model. This model is based on the assumption thatcompressed water in the SG is saturated at the beginning and decompresses into the two-phase regionwhere saturated vapor forms, creating a mixture of steam bubbles in water by bulk boiling. The numericalcalculations were performed for two cases of which the outflow boundary conditions aredifferent from each other; one is specified as the direct blowdown discharge to the atmosphere and theother is specified as the blowdown discharge to an extended calculation domain with atmosphericpressure on its boundary. The present simulation results obtained using the two different outflowboundary conditions were discussed through a comparison with the predictions using a simple nonflashingmodel neglecting the effects of phase change. In addition, the applicability of each of thenon-flashing water discharge and saturated water flashing models for the confirmatory assessments ofnew SG designs was examined.
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참고문헌 (23)
참고문헌 신청
S. Gallardo / 2012 / Simulation of a main steam line break with steam generator tube rupture using trace / Proceedings of the PHYSOR :2131~2144
L. Wolf / 1982 / Experimental results of coupled fluid-structure interactions during blowdown of the HDR-vessel and comparisons with pre- and post-test predictions / Nucl. Eng. Des 70:269~308
P. Saha / 1993 / Numerical simulation of pressure wave time history inside a steam generator in the event of main steam line break and feedwater line break transients / Proceedings of the Transient Phenomena in Nuclear Reactor Systems, ASME HTD-vol. 245/NE 11:131~140
H. Tinoco / 2002 / Three-dimensional modeling of a steam-line break in a boiling water reactor / Nucl. Sci. Eng 140:152~164
K.H. Kang / 2011 / Experimental study on the blowdown load during the steam generator feedwater line break accident in the evolutionary pressurized water reactor / Ann. Nucl. Ener 38:953~963
L. Wolf / 1982 / Experimental results of coupled fluid-structure interactions during blowdown of the HDR-vessel and comparisons with pre- and post-test predictions / Nucl. Eng. Des 70:269~308
P. Saha / 1993 / Numerical simulation of pressure wave time history inside a steam generator in the event of main steam line break and feedwater line break transients / Proceedings of the Transient Phenomena in Nuclear Reactor Systems, ASME HTD-vol. 245/NE 11:131~140
H. Tinoco / 2002 / Three-dimensional modeling of a steam-line break in a boiling water reactor / Nucl. Sci. Eng 140:152~164
K.H. Kang / 2011 / Experimental study on the blowdown load during the steam generator feedwater line break accident in the evolutionary pressurized water reactor / Ann. Nucl. Ener 38:953~963
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