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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.3
- 수록면
- 1,029 - 1,040 (12page)
- DOI
- https://doi.org/10.1016/j.net.2020.08.022
이용수
초록· 키워드
오류제보하기
For the structural integrity evaluation of pressurized water reactor (PWR) steam generator (SG) tubessubjected to transient hydraulic loading, determination of the tube-to-tube gap velocity and staticpressure distributions along the tubes is prerequisite. This paper addresses both computational fluiddynamics (CFD) and analytical approaches for predicting the tube-to-tube gap velocity and static pressure distributions during blowdown following a feedwater line break (FWLB) accident at a PWR SG. Firstof all, a comparative study on CFD calculations of the transient velocity and pressure distributions in theSG secondary sides for two different models having 30 or no tubes is performed. The result shows thatthe velocities of sub-cooled water flowing between any adjacent two tubes of a tubed SG model duringblowdown can be roughly estimated by applying the specified SG secondary side porosity to those of theno-tubed SG model. Secondly, simplified analytical approximate solutions for the steady twodimensional SG secondary flow velocity and pressure distributions under a given discharge flowrateare derived using a line sink model. The simplified analytical solutions are validated by comparing themto the CFD calculations
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등록된 정보가 없습니다.
참고문헌 (14)
참고문헌 신청
United States Nuclear Regulatory Commission / 2014 / NUREG-0800, Standard Review Plan, 3.9.3 ASME CODE CLASS 1, 2, and 3 COMPONENT, SUPPORTS, and CORE SUPPORT STRUCTURES, USNRC
A. Ksinghal / 1991 / A review of thermal hydraulic analysis methodology for PWR steam generators and ATHOS3 code applications / Prog. Nucl. Energy 25(1):7~70
J. C. Jo / 1999 / Fluidelastic instability analysis of operating nuclear steam generator U-tubes / NED 193(1-2):55~71
Y. Ferng / 2008 / CFD investigating the impacts of changing operating conditions on the thermal-hydraulic characteristics in a steam generator / Appl. Therm. Eng 28(5-6):414~422
Y. Yang / 2013 / Computational fluid dynamics investigation of thermalehydraulic characteristics for a steam generator with and without tube support plates / Proc. IME C J. Mech. Eng. Sci 227(12):2897~2911
A. Ksinghal / 1991 / A review of thermal hydraulic analysis methodology for PWR steam generators and ATHOS3 code applications / Prog. Nucl. Energy 25(1):7~70
J. C. Jo / 1999 / Fluidelastic instability analysis of operating nuclear steam generator U-tubes / NED 193(1-2):55~71
Y. Ferng / 2008 / CFD investigating the impacts of changing operating conditions on the thermal-hydraulic characteristics in a steam generator / Appl. Therm. Eng 28(5-6):414~422
Y. Yang / 2013 / Computational fluid dynamics investigation of thermalehydraulic characteristics for a steam generator with and without tube support plates / Proc. IME C J. Mech. Eng. Sci 227(12):2897~2911
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