An experimental investigation of critical flow rates of subcooled water through short pipes with small diameters

Journal Article · Sun Dec 01 04:00:00 EST 1996 · International Communications in Heat and Mass Transfer

DOI:https://doi.org/10.1016/S0735-1933(96)00087-5· OSTI ID:418045

Chun, M H; Park, C K ^[1]; Park, J W ^[2]

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1. Korea Advanced Inst. of Science and Technology, Taejon (Korea, Republic of). Dept. of Nuclear Engineering
2. Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

Critical two-phase flow rates of subcooled water through short pipes (L < 400 mm) with small diameters (D < 7.15 mm) have been experimentally investigated for wide ranges of subcooling (0 {approximately} 199 C) and pressure (0.5 {approximately} 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 effects 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 ({Delta}T*{sub sub}) curve. An empirical correlation expressed in terms of a dimensionless subcooling ({Delta}T*{sub sub}) 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 679 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. This study is applicable to LOCA analyses in LWR.

• OSTI ID: 418045
• Journal Information: International Communications in Heat and Mass Transfer, Journal Name: International Communications in Heat and Mass Transfer Journal Issue: 8 Vol. 23; ISSN 0735-1933; ISSN IHMTDL
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
CRITICAL FLOW
EXPERIMENTAL DATA
HYDRAULICS
LOSS OF COOLANT
PIPES
TWO-PHASE FLOW
WATER COOLED REACTORS