1 |
H.K. Fauske: "Contribution to the Theory of Two-phase, One Component Critical Flow," ANL-6633 (1962)
|
2 |
F.R. Zaloudek: "Critical Flow of Hot Water through Short Tubes," General Electric, HW-77594 (1963)
|
3 |
F.J. Moody: "Maximum Flow Rate of a Single Component, Two-Phase Mixture." ASME Journal of Heat Transfer, pp. 134-142 (1965)
|
4 |
R.E. Henry: "A Study of One- and Two-Component, Two-Phase Critical Flows at Low Qualities," ANL-7430 (1968)
|
5 |
G.L. Sozzi and W.A. Sutherland: "Critical Flow of Saturated and Subcooled Water at High Pressure," NEDO-13418 (1975)
|
6 |
U.S. NRC: "The Marviken Full-Scale Critical-Flow Tests,"NUREG/CR-2671, MXC-301 (1982)
|
7 |
M-H. Chun, C-K. Park, and J-W. Park, "An Experimental Investigation of Critical Flow Rates of Subcooled Water Through Short Pipes with Small Diameters," Int. Comm. in Heat and Mass Transfer, Vol. 23, No. 8, pp. 1053-1064 (1996)
DOI
ScienceOn
|
8 |
C-K. Park, "An Experimental Investigation of Critical Flow Rates of Subcooled Water through Short Pipes with Small Diameters," Ph. D. Thesis, KAIST, Korea (1997)
|
9 |
C-K. Park, J-W. Park, M-K. Chung, and M-H. Chun: "An Empirical Correlation for Critical Flow Rates of Subcooled Water through Short Pipes with Small Diameters," Nuc. Eng. and Tech., Vol. 29, No. 1, pp. 35-44 (1997)
|
10 |
C-K. Park, S. Cho, T-S. Kwon, S-K. Yang, and M-K. Chung: "An Experimental Investigation of Maximum Flow Rates of Subcooled Water through Square Edge Orifices with Small Diameters," NTHAS2: Second Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety, Fukuoka, Japan, Oct. 15-18 (2000)
|
11 |
H-S. Park, N-H. Choi, S-K. Chang, C-H. Chung, S-J. Yi, C-K. Park, and M-K. Chung: "Experimental Study on a Two-phase Critical Flow with a Non-Condensable Gas at High Pressure Conditions," Int. J. Multiphase Flow, 33, pp. 1222-1236 (2007)
DOI
|
12 |
W-P. Baek, and Y-S. Kim, "Accident Simulation ATLAS for APWRs," Nuclear Engineering International, 53, pp. 21-25 (2008)
|
13 |
S-T. Lee, "Horizontal Disperse Flows: Disperse and Continuous Phase Velocity,"Interim Presentation, Korea Atomic Energy Research Institute (2013)
|
14 |
H-S. Park, S-J. Yi, and C-H. Song," SMR Accident Simulation in Experimental Test Loop," Nuclear Engineering International, November, pp. 12-15 (2013)
|
15 |
R.T. Lahey, Jr. and F.J. Moody, The Thermal-Hydraulics of a Boiling Water Reactor, 3rd Printing, American Nuclear Society (1984)
|
16 |
F.J. Moody, "Maximum Two-Phase Vessel Blowdown from Pipes," ASME Journal of Heat Transfer, pp. 285-295 (1966)
|
17 |
B-D. Chung et al., "MARS Code Manual, Volume II: Input Requirements," KAERI/TR-2811/2004, Korea Atomic Energy Research Institute (2007)
|
18 |
U.S. NRC, "TRACE V5.0 User's Manual, Volume 1: Input Specification," Office of Nuclear Regulatory Research, U.S. NRC (2008)
|
19 |
F.J. Moody, "Maximum Discharge Rate of Liquid-Vapor Mixtures from Vessels, Non-Equilibrium Two-Phase Flows," ASME Symp.,American Society of Mechanical Engineers, pp. 27-36 (1975)
|
20 |
I.E. Idelchik, Handbook of Hydraulic Resistance, 3rd Edition, Begell House, Inc. (1996)
|