AI Chat Paper
Note: Please note that the following content is generated by AMiner AI. SciOpen does not take any responsibility related to this content.
{{lang === 'zh_CN' ? '文章概述' : 'Summary'}}
{{lang === 'en_US' ? '中' : 'Eng'}}
Chat more with AI
Article Link
Collect
Submit Manuscript
Show Outline
Outline
Show full outline
Hide outline
Outline
Show full outline
Hide outline
Research Article | Open Access

Effect of interfacial drag force model on code prediction for upward adiabatic two-phase bubbly flow in vertical channels

Takashi Hibiki1( )Tetsuhiro Ozaki2
School of Nuclear Engineering, Purdue University, 400 Central Drive, West Lafayette IN 47907-2017, USA
Nuclear Fuel Industries, Ltd., 33-5 Tsurumi Chuo, Tsurumi-ku, Yokohama, Kanagawa 230-0051, Japan
Show Author Information
An erratum to this article is available online at:

Abstract

Accurate modeling of the interfacial drag force is one of the keys to predicting thermo-fluid parameters using one-dimensional nuclear thermal-hydraulic system analysis code architected through the two-fluid model. The interfacial drag force appears in the interfacial momentum transfer term and governs the velocity slip or the relative velocity between gas and liquid phases. The most straightforward method to model the interfacial drag force is to model the force through the drag law (drag law approach). A drag coefficient and interfacial area concentration should be given to close the interfacial drag force model. Among them, the modeling of the interfacial area concentration has been one of the weakest links in the interfacial drag force modeling due to the lack of reliable data covering a wide test condition including prototypic nuclear reactor conditions and lack of physically sound interfacial area model. To avoid a considerable uncertainty in the prediction of the interfacial area concentration, Andersen and Chu (1982) proposed the interfacial drag force model using the drift-flux parameters (Andersen approach). The Andersen approach is practical for the simulation of a slow transient flow and a steady flow. Major system analysis codes such as USNRC TRACE have adopted the Andersen approach in the interfacial drag force modeling. Some attempts to improve the code performance have been considered using the drag law approach with the interfacial area transport equation. The dynamic modeling of the interfacial area concentration has the potential to improve the prediction accuracy of the interfacial area concentration in a transient flow and developing flow. Due to the importance of the improved interfacial drag force modeling, the implementation and evaluation of the interfacial area transport equation in USNRC TRACE code has been performed by Talley et al. (2011, 2013). The study claimed that the introduction of the interfacial area transport equation into the TRACE code improved the code performance in an adiabatic bubbly flow analysis significantly. The present study assessed the code calculation made by Talley et al. (2011) and identified several issues in the code calculation results. The present study analytically demonstrated that the drag law approach became identical with the Andersen approach for the distorted particle regime (or a major bubble shape regime in bubbly flow) due to the balancing-out of the interfacial area concentration (or bubble size) in the numerator and denominator of the interfacial drag force formulation. The code calculation using TRAC code endorsed the analytical assessment of the insignificant or no merit of the interfacial area transport equation in the code performance of the adiabatic bubbly flow analysis. The present study also pointed out the inconsistency of the code calculation made by Talley et al. (2011).

References

 
Andersen, J. G. M., Chu, K. H. 1982. BWR refill-reflood program task 4.7: Constitutive relations for shear and heat transfer for the BWR version of TRAC (No. NUREG/CR--2134). General Electric Co.
 
Borkowski, J. A., Wade, N. L., Rouhani, S. Z., Shumway, R. W., Weaver, W. L., Rettig, W. H., Kullberg, C. L. 1992. TRAC-BF1/MOD1 models and correlations (No. NUREG/CR--4391). Nuclear Regulatory Committee, United States.
 
Chuang, T. J., Hibiki, T. 2015. Vertical upward two-phase flow CFD using interfacial area transport equation. Prog Nucl Energ, 85: 415-427.
 
Fu, X. Y. 2001. Interfacial area measurement and transport modeling in air-water two-phase flow. Ph.D. Thesis. Purdue University.
 
Hibiki, T., Ishii, M. 1999. Experimental study on interfacial area transport in bubbly two-phase flows. Int J Heat Mass Tran, 42: 3019-3035.
 
Hibiki, T., Ishii, M. 2002a. Distribution parameter and drift velocity of drift-flux model in bubbly flow. Int J Heat Mass Tran, 45: 707-721.
 
Hibiki, T., Ishii, M. 2002b. Interfacial area concentration of bubbly flow systems. Chem Eng Sci, 57: 3967-3977.
 
Hibiki, T., Ishii, M. 2009. Interfacial area transport equations for gas-liquid flow. J Comput Multiphase Flows, 1: 1-22.
 
Hibiki, T., Lee, T. H., Lee, J. Y., Ishii, M. 2006. Interfacial area concentration in boiling bubbly flow systems. Chem Eng Sci, 61: 7979-7990.
 
Hibiki, T., Ozaki, T. 2017. Modeling of void fraction covariance and relative velocity covariance for upward boiling flow in vertical pipe. Int J Heat Mass Tran, 112: 620-629.
 
Hibiki, T., Schlegel, J. P., Ozaki, T., Miwa, S., Rassame, S. 2018. Simplified two-group two-fluid model for three-dimensional two-phase flow computational fluid dynamics for vertical upward flow. Prog Nucl Energ, 108: 503-516.
 
Ishii, M., Hibiki, T. 2011. Thermo-Fluid Dynamics of Two-Phase Flow, 2nd edn. New York: Springer.
 
Kelly, J. M. 1997. Thermal-hydraulic modeling needs for passive reactors. In: Proceedings of the OECD/CSNI Specialist Meeting on Advanced Instrumentation and Measurement Techniques.
 
Kim, S. 1999. Interfacial area transport equation and measurement of local interfacial characteristics. Ph.D. Thesis. Purdue University.
 
Lin, C. H., Hibiki, T. 2014. Databases of interfacial area concentration in gas-liquid two-phase flow. Prog Nucl Energ, 74: 91-102.
 
Mortensen, G. A. 1995. Long-term plan for NRC thermal-hydraulic code development. Report to US NRC under Contract No. DE-AC07-94ID13223.
 
NRC US. 2008. TRACE V5.0 Theory manual. Field equations, solutions methods, and physical models. Nuclear Regulatory Committee, United States.
 
Ozaki, T., Hibiki, T., Miwa, S., Mori, M. 2018. Code performance with improved two-group interfacial area concentration correlation for one-dimensional forced convective two-phase flow simulation. J Nucl Sci Technol, 55: 911-930.
 
Ozar, B., Dixit, A., Chen, S. W., Hibiki, T., Ishii, M. 2012. Interfacial area concentration in gas-liquid bubbly to churn-turbulent flow regime. Int J Heat Fluid Fl, 38: 168-179.
 
Ransom, V. H., Trapp, J., Wagner, R. 2001. RELAP5/MOD3.3 code manual volume IV: Models and correlations. Information System Laboratories, Nuclear Regulatory Committee, United States.
 
Schlegel, J. P., Hibiki, T. 2015. A correlation for interfacial area concentration in high void fraction flows in large diameter channels. Chem Eng Sci, 131: 172-186.
 
Shen, X. Z., Hibiki, T. 2015. Interfacial area concentration in gas-liquid bubbly to churn flow regimes in large diameter pipes. Int J Heat Fluid Fl, 54: 107-118.
 
Talley, J. D., Kim, S., Mahaffy, J., Bajorek, S. M., Tien, K. 2011. Implementation and evaluation of one-group interfacial area transport equation in TRACE. Nucl Eng Des, 241: 865-873.
 
Talley, J. D., Worosz, T., Kim, S., Bajorek, S. M., Tien, K. 2013. Effect of bubble interactions on the prediction of interfacial area in TRACE. Nucl Eng Des, 264: 135-145.
 
Wu, Q., Kim, S., Ishii, M., Beus, S. G. 1998. One-group interfacial area transport in vertical bubbly flow. Int J Heat Mass Tran, 41: 1103-1112.
Experimental and Computational Multiphase Flow
Pages 212-224
Cite this article:
Hibiki T, Ozaki T. Effect of interfacial drag force model on code prediction for upward adiabatic two-phase bubbly flow in vertical channels. Experimental and Computational Multiphase Flow, 2020, 2(4): 212-224. https://doi.org/10.1007/s42757-019-0040-z

854

Views

6

Crossref

9

Web of Science

6

Scopus

Altmetrics

Received: 18 March 2019
Revised: 01 July 2019
Accepted: 01 July 2019
Published: 04 January 2020
© Tsinghua University Press 2019
Return