Drift-flux model in a sub-channel of rod bundle geometry

International Journal of Heat and Mass Transfer

Volumn 52, Issue 13-14, 2009, Pages 3032-3041

  Enrique Julia, J ^a   Hibiki, Takashi ^b   Ishii, Mamoru ^b   Yun, Byong Jo ^c   Park, Goon Cherl ^d  

^a UNIVERSITAT JAUME I   (Spain)

^b PURDUE UNIVERSITY   (United States)

^c Korea Atomic Energy Research Institute   (South Korea)

^d Seoul National University   (South Korea)

Author keywords

Drift velocity; Drift flux model; Rod bundle; Sub channel; Subcooled boiling flow; Void fraction

Indexed keywords

DRIFT VELOCITY; DRIFT-FLUX MODEL; ROD BUNDLE; SUB-CHANNEL; SUBCOOLED BOILING FLOW;

BOILING LIQUIDS; COMPUTATIONAL GEOMETRY; FLUID DYNAMICS; PIPE; TWO PHASE FLOW; VELOCITY; VOID FRACTION;

CONSTITUTIVE EQUATIONS;

EID: 64749094139     PISSN: 00179310     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.ijheatmasstransfer.2009.02.012     Document Type: Article

References (28)

1. G. Espinosa-Paredes, A. Nuñez-Carrera, SBWR model for steady-state and transient analysis, Science and Technology of Nuclear Installations 2008 (2008), Article ID 428168.
2. Zuber N., and Findlay J.A. Average volumetric concentration in two-phase flow systems. J. Heat Transfer 87 (1965) 453-468
3. M. Ishii, One-dimensional drift-flux model and constitutive equations for relative motion between phases in various two-phase flow regimes, ANL-77-47, USA, 1977.
4. Ishii M., and Hibiki T. Thermo-fluid Dynamics of Two-phase Flow (2006), Springer, New York, USA
5. Hibiki T., and Ishii M. Distribution parameter and drift velocity of drift-flux model in bubbly flow. Int. J. Heat Mass Transfer 45 (2002) 707-721
6. Hibiki T., and Ishii M. One-dimensional drift-flux model for two-phase flow in a large diameter pipe. Int. J. Heat Mass Transfer 46 (2003) 1773-1790
7. Goda H., Hibiki T., Kim S., Ishii M., and Uhle J. Drift flux model for downward two-phase flow. Int. J. Heat Mass Transfer 46 (2003) 4835-4844
8. Coddington P., and Macian R. A study of the performance of void fraction correlations used in the context of drift-flux two-phase flow models. Nucl. Eng. Des. 215 (2002) 199-216
9. Bestion D. The physical closure laws in the CATHARE code. Nucl. Eng. Des. 124 (1990) 229-245
10. Venkateswararao P., Semiat R., and Dukler A.E. Flow pattern transition for gas-liquid flow in a vertical rod bundle. Int. J. Multiphase Flow 8 (1982) 509-524
11. Chexal B., Lellouche G., Horowitz J., and Healzer J. A void fraction correlation for generalized applications. Prog. Nucl. Energy 27 (1992) 255-295
12. B. Chexal, G. Lellouche, A full range drift-flux correlation for vertical flows (Revision 1), EPRI Report NP-3989-SR, USA, 1986.
13. A. Inoue, T. Kurosu, M. Yagi, S. Morooka, A. Hoshide, T. Ishizuka, K. Yoshimura, In-bundle void measurement of a BWR fuel assembly by a X-ray CT scanner: assessment of BWR design void correlation and development of new void correlation, in: Proc. of the ASME/JSME Nuclear Engineering Conference, 1993.
14. S. Morooka, A. Inoue, M. Oishi, T. Aoki, K. Nagaoka, H. Yoshida, In-bundle void measurement of BWR fuel assembly by X-ray CT scanner, in: Proc. of ICONE-1, Paper 38, 1991.
15. D. Maier, P. Coddington, Review of wide range void correlations against an extensive data base of rod bundle void measurements, in: Proc. of ICONE-5, Paper 2434, 1997.
16. Hibiki T., Situ R., Mi Y., and Ishii M. Modeling of bubble-layer thickness for formulation of one-dimensional interfacial area transport equation in subcooled boiling two-phase flow. Int. J. Heat Mass Transfer 46 (2003) 1409-1423
17. Yun B.J., Park G.C., Julia J.E., and Hibiki T. Flow structure of sub-cooled boiling water flow in a sub-channel of 3 × 3 rod bundles. J. Nucl. Sci. Technol. 45 (2008) 402-422
18. Mitsutake T., Morooka S., Suzuki K., Tsunoyama S., and Yoshimura K. Void fraction estimation within rod bundles based on three-fluid model and comparison with X-ray CT void data. Nucl. Eng. Des. 120 (1990) 203-212
19. Kumamaru H., Kondo M., Murata H., and Kukita Y. Void-fraction distribution Ander high-pressure boil-off conditions in rod bundle geometry. Nucl. Eng. Des. 150 (1994) 95-105
20. R. Deruaz, P. Clement, J.M. Veteau, Study of two-dimensional effects in the core of a light water reactor during the ECC's phase following a loss of coolant accident, EUR 10076 EN, Commissariat a l'Energie Atimique, Centre d'Etude Nucleaires de Grenoble, Service des Transferts Thermiques, Grenoble, France, 1985.
21. Dreier J., Analytis G., and Chawla R. NEPTUN-III reflooding and boil-off experiments with an LWHCR fuel bundle simulator: experimental results and initial core assessment efforts. Nucl. Technol. 80 (1988) 93-106
22. Y. Anoda, Y. Kukita, K. Tasaka, Void fraction distribution in rod bundle under high pressure conditions, in: Proc. ASME Winter Annual Meeting, Advances in Gas-Liquid Flows, 1990.
23. Anklam T.M., and Miller R.F. Void fraction under high pressure, low flow conditions in rod bundle geometry. Nucl. Eng. Des. 75 (1983) 99-108
24. Ozar B., Jeong J.J., Dixit A., Juliá J.E., Hibiki T., and Ishii M. Flow structure of gas-liquid two-phase flow in an annulus. Chem. Eng. Sci. 63 (2008) 3998-4011
25. Tomiyama A., Nakahara Y., Adachi Y., and Hosokawa S. Shapes and rising velocities of single bubbles rising though a inner subchannel. J. Nucl. Sci. Technol. 40 (2003) 136-142
26. Wallis G.B. One-dimensional Two-phase Flow (1969), McGraw Hill
27. Carlucci L.N., Hammouda N., and Rowe D.S. Two-phase turbulent mixing and buoyancy drift in rod bundles. Nucl. Eng. Des. 227 (2004) 65-84
28. Hibiki T., Lee T.H., Lee J.Y., and Ishii M. Interfacial area concentration in boiling bubbly flow systems. Chem. Eng. Sci. 61 (2006) 7979-7990