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An Empirical Correlation for Critical Flow Rates of Subcooled Water Through Short Pipes with Small Diameters

Park, Choon-Kyung   (Korea Atomic Energy Research Institute Thermal Hydraulics DepartmentCC0186830  ); Park, Jee-Won   (Korea Atomic Energy Research Institute Thermal Hydraulics DepartmentCC0186830  ); Chung, Moon-Ki   (Korea Atomic Energy Research Institute Thermal Hydraulics DepartmentCC0186830  ); Chun, Moon-Hyun   (Korea Advanced Institute of Science and TechnologyUU0001375  );
  • 초록

    Critical too-Phase flow rates of subcooled water through Short Pipes (L 140039n) with small diameters (D $\leq$ 7.15 min) have been experimentally investigated for wide ranges of subcooling (0~199 $^{\circ}C$ ) and pressure (0.5~2.0 MPa). To examine the effects of various parameters (i.e., the location of flashing inception, the degree of subcooling, the stagnation temperature and pressure, and the pipe size) on the critical two-phase flow rates of subcooled water through short pipes with small diameters, a total of 135 runs were made for various combinations of test parameters using four different L/D test sections. Experimental results that show effect of various parameters on subcooled critical two phase flow rates are presented in the form of graphs such as the dimensionless mass flux ( $G^{*}$ ) versus the dimensionless subcooling ( $T_{sub}$ $^{*}$ ) curve. An empirical correlation expressed in terms of a dimensionless subcooling is also obtained for subcooled two-phase flow rates through present test sections. Comparisons between the mass fluxes calculated by present correlation and a total of 755 selected experimental data points of 9 different investigators show that the agreement is fairly good except for very low subcooling data obtained from small L/D (less than 10) orifices.s.s.s.


  • 참고문헌 (12)

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    1. 1980 "Reflood Experiments with Horizontal and Vertical Flow Channels" Journal of the Korean Nuclear Society = 원자력학회지 12 (3): 153~162    
    2. 2003 "수조내 증기제트 응축현상 제고찰" 에너지공학 = Journal of energy engineering 12 (2): 74~83    
    3. 2006 "PARAMETRIC STUDIES ON THERMAL HYDRAULIC CHARACTERISTICS FOR TRANSIENT OPERATIONS OF AN INTEGRAL TYPE REACTOR" Nuclear engineering and technology : an international journal of the Korean Nuclear Society 38 (2): 185~194    
    4. 2008 "APR1400 모의를 위한 ATLAS 안전주입탱크의 주입 성능에 관한 특성 시험" 에너지공학 = Journal of energy engineering 17 (2): 67~76    
  • Park, Jee-Won (1)

  • 정문기 (22)

  • Chun, Moon-Hyun (28)

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