An improved horizontal flow regime map for the 1-D module of WCOBRA/TRAC-TF2

International Conference on Advances in Nuclear Power Plants, ICAPP 2008

Volumn 3, Issue , 2008, Pages 1474-1485

  Frepoli, Cesare ^a   Liao, Jun ^a   Ohkawa, Katsuhiro ^a  

^a WESTINGHOUSE ELECTRIC COMPANY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BEST ESTIMATES; COBRA-TF; D-MODULES; DISPERSED FLOW; FLOW REGIME MAP; FULL SPECTRUM; HORIZONTAL FLOWS; PHYSICALLY BASED; REGIME MAP; SAFETY ANALYSIS; SEPARATED FLOWS; SMALL BREAK; STATISTICAL TREATMENT; STRATIFIED FLOWS; TEST DATA; TWO-FLUID; WESTINGHOUSE;

LOSS OF COOLANT ACCIDENTS; NUCLEAR ENERGY; NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; PRESSURIZED WATER REACTORS; THREE DIMENSIONAL;

FLOW OF WATER;

EID: 70349878808     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (29)

1. Y. ANODA, Y. Kukita, N. Nakamura and K. Tasaka, "Flow Regime Transition in High-Pressure Large- Diameter Horizontal Two-Phase Flow," Proc. of 26th ASME/AICHE/ANS National Heat Transfer Conference, pp 61-69, Philadelphia, (1989).
2. H. ASAKA, at. al., "Improvement of TRAC-PFI Interfacial Drag Model for Analysis of High-Pressure Horizontally- Stratified Two-Phase Flow," Journal of Nuclear Science and Technology. Vol. 28, No. 1, pp. 33-44 (1991).
3. K. H. ARDRON and W.M. Bryce, "Assessment of horizontal stratification entrainment model in RELAP5/MOD2 by comparison with separate effects experiments," Nuclear Engineering and Design, Vol. 122, pg. 263-271, 1990
4. D. BESTION, "The physical closure laws in the CATHARE code," Nuclear Engineering and Design, Vol.124, pg. 229-245, 1990
5. C. FREPOLI, "Review Article - An Overview of Westinghouse Realistic Large Break LOCA Evaluation Model," Science and Technology of Nuclear Installations, Vol.2008, Hindawi Publishing Corporation, Article ID 498737.
6. M. KAWAJI, Y. Anoda, H. Nakamura and T. Tasaka, "Phase and velocity distributions and holdup in high- pressure steamlwater stratified flow in a large diameter horizontal pipe," int. J. Multiphase Flow, Vol.13, No 2,pp. 145-159, 1987
7. T. KUIUTA, H. Asaka, Y. Mimura, Y. Anoda, M. Ishiguro, T. Nemoto, K. Tasaka, "Developmental Assessment of RELAP5/MOD3 Code Against ROSA IV TPTF Horizontal Two-Phase Experiments," JAERI-M-90-053, (1990)
8. J. LIAO and C. Frepoli., "Development of a condensation heat transfer model for the analysis of ECC injection in Cold Leg during Small and Intermediate Break LOCA," Proc. Of the 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12), Log Number: 170 Sheraton Station Square, Pittsburgh, Pennsylvania, U.S.A. September 30-October 4, 2007.
9. D.R. LILES at al., 'TRAC-PD2, An Advanced Best-Estimate Computer Program for Pressurized Water Reactor Loss-of-Coolant Accident Analysis," NUREGICR-2054 (1981)'
10. J. H. LTh4EHAN, M. Petrick, and M. M. El-Wakil, "The Condensation of Saturated Vapor on a Subcooled Film During Stratified Flow," Chem. Eng. Symp. Series, Vol.66 (102), pp. 11-20 (1972).
11. J. M. MANDHANE, G A. Gregory, and K. Aziz, "A Flow Pattern Map for Gas Liquid Flow in Horizontal Pipes," int. J. Multiphase Flow, 1, pp. 537-553 (1974).
12. Y. M. MOON and H. C. No, "Off-Take and Slug Transition at T-Junction of Vertical-Up Branch in the Horizonthal Pipe," Journal and Nuclear Science and Technology, Vol.40, No 5, pp. 317-324, 2003.
13. H. NAKAMURA, Y. Anoda and Y. Kukita, "Flow Regime Transition in High-Pressure Steam-Water Horizontal Pipe Two-Phase Flow," ANS Proceeding of 1991 National Heat Transfer Conference, Minneapolis, 269-276, 1991.
14. H. NAKAMURA, Y. Kukita and K. Tasaka, "An Evaluation of Bernoulli Effect on Slugging in Horizontal Two-Phase Flow," Journal of Nuclear Science and Technology, Vol.31, No. 1, pp. 113-121, 1994.
15. H. NAKAMIURA, Y. Kukita and K. Tasaka, "Flow Regime Transition to Wavy Dispersed Flow for High- Pressure SteamlWater Two-Phase Flow in Horizontal Pipe," Journal of Nuclear Science and Technology, Vol.32, No. 7, pp. 64 1-652, (1995)
16. H. NAKAMURA, Y. Kukita and K. Tasaka, "Interfacial Friction Factor for High-Pressure Steam/Water Stratified-Wavy Flow in Horizontal Pipe," Journal of Nuclear Science and Technology, Vol.32, No. 9, pp. 868-879, (1995)
17. A. OHNUKI, H. Adachi, andY. Murao, "Scale Effects on Countercurrent Gas-Liquid Flow in Horizontal Tube Connected to Inclined Riser," Transaction ANS 1987 National Heat Transfer Conference, pp. 40-49, Pittsburgh, Pennsylvania, August 9-12, 1987.
18. C.Y. PAIK and L.E. Hochreiter, "Analysis of FLECHT-SEASET 163 Rod Bundle Data Using COBRA-TF," NUREG/CR-4166 (1986).
19. RELAP5/MOD3, Code Manual, Volume IV: Models and Correlations // NUREG/CR-5535-V4. Idaho. 1995.
20. H. C. SIMPSON, D. H. Rooney, E. Gratton and F. A. A. Al-Samarral, "Two-Phase Flow in Large Diameter Horizontal Tubes," NEL Report N.677 1991
21. C. SMOGLIE and J. Reimann, "Two-Phase Flow Through Small Branches in Horizontal Pipe With Stratified Flow," int. J. Multiphase Flow, Vol.12, N. 4, pp. 609-625 (1986).
22. Y. TAITEL and A. Dukler, "A model for predicting flow regime transitions in horizontal and near horizontal gas-liquid flow," AIChE Journal, Vol.22, No. 1, pp. 47-54, 1976.
23. Y. TAITEL, N. Lee and A. E. Dukler, "Transient Gas- Liquid Flow in Horizontal Pipes: Modeling the Flow Pattern Transitions," A1ChE Journal, Vol.24, No. 5, 1978
24. TRAC-PFIIMOD2, Theory Manual //NM 87545. Los Alamos. 1993.
25. J. W. SPORE, J. S. Elson, S. J. Jolly Woodruff, T. D. Knight, J. C. Lin, R. A. Nelson, K. O. Pasamehmetoglu, R. G. Steinke, C. Unal, J. H. Mahaffy and C. Murray, "TRAC MJFORTRAN 90 (VERSION 3.0) Theory Manual," LA UR 00 910 (2000)
26. M. J. THURGOOD et al., "COBRA/TRAC - A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems," NUREG/CR-3046 (1983)
27. M. J. THURGOOD et al., "COBRA-TF Development," Proc. Of 8th Water Reactor Safety Information Meeting. (1980)
28. M. Y. YOUNG S. M. Bajorek, M. E Nissley and L. E Hochreiter, "Application of code scaling applicability and uncertainty methodology to the large break loss of coolant," Nuclear Engineering and Design, 186, pp. 39-52, (1998).
29. Yu. V. YUDOV, "The KORSAR Computer Code Modeling of Stratified Two-Phase Flow Hydrodynamics in Horizontal Pipes," Proceedings of ICONEJO-22096, 10th International Conference on Nuclear Engineering, Arlington, VA, April 14-18, (2002)