Assessment of a Theoretical Model for Predicting Forced Convective Critical Heat Flux in Rod Bundles

A theoretical model for predicting forced convective critical heat flux (CHF) in rod bundles was proposed, which is based on the bubble crowding phenomenon. The theoretical model applied to the rod bundle is based on the Weisman-Pei's basic tube model. In order to make it suitable for Pressurized Water Reactor (PWR) in rod bundles, the flow and heat transfer characteristics of rod bundles are considered, including velocity distribution, flow patterns, grid effect on CHF and turbulent intensity. The theoretical model has been applied together with the subchannel code ATHAS for assessing against uniformly heated CHF data obtained through a 5x5 rod bundle, and good agreement has been observed.

[1]  E. Abedini,et al.  Prediction of critical heat flux in flow boiling process under the effect of different operating parameters , 2020 .

[2]  T. Sattelmayer,et al.  Critical Heat Flux in Flow Boiling—Review of the Current Understanding and Experimental Approaches , 2017 .

[3]  Liu We.  Study on Reactor Thermal-hydraulic Sub-channel Analysis Code ATHAS , 2014 .

[4]  I. Kataoka,et al.  Study on Analytical Prediction of Forced Convective CHF in the Wide Range of Quality , 2002 .

[5]  H. Nariai,et al.  Study of Critical Heat Flux Mechanism in Flow Boiling Using Bubble Crowding Model , 2001 .

[6]  Soon-Heung Chang,et al.  A mechanistic critical heat flux model for wide range of subcooled and low quality flow boiling , 1999 .

[7]  Takuji Nagayoshi,et al.  Spacer Effect Model for Subchannel Analysis -Turbulence Intensity Enhancement due to Spacer- , 1998 .

[8]  A. Mariani,et al.  Rationalization of existing mechanistic models for the prediction of water subcooled flow boiling critical heat flux , 1994 .

[9]  S. C. Lee,et al.  A critical review of predictive models for the onset of significant void in forced-convection subcooled boiling , 1993 .

[10]  S. Bankoff,et al.  Prediction of the onset of significant void in transient subcooled flow boiling , 1993 .

[11]  Joel Weisman,et al.  The Current Status of Theoretically Based Approaches to the Prediction of the Critical Heat Flux in Flow Boiling , 1992 .

[12]  Soon-Heung Chang,et al.  A critical heat flux model based on mass, energy, and momentum balance for upflow boiling at low qualities , 1989 .

[13]  J. Weisman,et al.  A phenomenological model for prediction of critical heat flux under highly subcooled conditions , 1988 .

[14]  J. Weisman,et al.  Prediction of the critical heat flux in flow boiling at intermediate qualities , 1986 .

[15]  J. Weisman,et al.  Prediction of critical heat flux in flow boiling at low qualities , 1983 .

[16]  Raphael Semiat,et al.  Flow pattern transition for gas-liquid flow in a vertical rod bundle , 1982 .

[17]  W. Leech,et al.  Heat-Transfer Augmentation in Rod Bundles Near Grid Spacers , 1982 .

[18]  F. Durst,et al.  On the motions of particles in turbulent flows , 1980 .

[19]  R. Azad,et al.  The structure of turbulent flow in triangular array rod bundles , 1975 .

[20]  S. Levy.  Forced convection subcooled boiling—prediction of vapor volumetric fraction , 1967 .

[21]  J. Laufer,et al.  The Structure of Turbulence in Fully Developed Pipe Flow , 1953 .