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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2021.4
- 수록면
- 1,100 - 1,108 (9page)
- DOI
- https://doi.org/10.1016/j.net.2020.09.017
이용수
초록· 키워드
오류제보하기
Supercritical water has great potential as a coolant for nuclear reactor. Its use will lead to higher thermalefficiency of Rankine cycle. However, in certain conditions heat transfer may get deteriorated which maylead to undesirable high clad surface temperature. It is necessary to estimate the operating conditions inwhich heat transfer deterioration (HTD) will take place, so as to establish thermal margins for safereactor operation. In the present work, the heat flux corresponding to onset of HTD for vertically upwardflow of supercritical water in a pipe is obtained over a wide range of system parameters, namely pressure,mass flux, and pipe diameter. This is done by performing large number of simulations using an inhouseCFD code, which is especially developed and validated for this purpose. The identification of HTDis based on observance of one or more peak/s in the computed wall temperature profile. The existingcorrelations for predicting the onset of HTD are compared against the results obtained by presentsimulations as well as available sets of experimental data. It is found that the prediction accuracy of thecorrelation proposed by Dongliang et al. is best among the existing correlations
목차
등록된 정보가 없습니다.
참고문헌 (33)
참고문헌 신청
I. L. Pioro / 2004 / Heat transfer to supercritical fluids flowing in channelsdempirical correlations(survey) / Nucl. Eng. Des 230:69~91
U. S. DOE / 2002 / A Technology Roadmap for Generation IV Nuclear Energy Systems / Nuclear Energy Research Advisory Committee and the Generation IV International Forum
E. W. Lemmon / 2007 / NIST Standard Reference Database 23: Reference Fluid Thermodynamic and Transport Properties-REFPROP
J. Jackson / 1979 / Influences of Buoyancy on Heat Transfer to Fluids Flowing in Vertical Tubes under Turbulent Conditions
K. Yamagata / 1972 / Forced convective heat transfer to supercritical water flowing in tubes / Int. J. Heat Mass Tran 15:2575~2593
U. S. DOE / 2002 / A Technology Roadmap for Generation IV Nuclear Energy Systems / Nuclear Energy Research Advisory Committee and the Generation IV International Forum
E. W. Lemmon / 2007 / NIST Standard Reference Database 23: Reference Fluid Thermodynamic and Transport Properties-REFPROP
J. Jackson / 1979 / Influences of Buoyancy on Heat Transfer to Fluids Flowing in Vertical Tubes under Turbulent Conditions
K. Yamagata / 1972 / Forced convective heat transfer to supercritical water flowing in tubes / Int. J. Heat Mass Tran 15:2575~2593
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