A Theoretical Critical Heat Flux Model for Rod Bundles Under Pressurized Water Reactor Conditions

[1]  N. Zuber,et al.  Average volumetric concentration in two-phase flow systems , 1965 .

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

[3]  C. Lee,et al.  A mechanistic critical heat flux model for subcooled flow boiling based on local bulk flow conditions , 1988 .

[5]  W. Hebel,et al.  A contribution to the hydrodynamics of boiling crisis in a forced flow of water , 1981 .

[6]  Y. Katto,et al.  An improved version of the generalized correlation of critical heat flux for the forced convective boiling in uniformly heated vertical tubes , 1984 .

[7]  R. Mesler,et al.  A mechanism supported by extensive experimental evidence to explain high heat fluxes observed during nucleate boiling , 1976 .

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

[9]  Y. Katto,et al.  A new hydrodynamic model of critical heat flux, applicable widely to both pool and forced convection boiling on submerged bodies in saturated liquids , 1983 .

[10]  R. Hino,et al.  Studies on heat transfer and flow characteristics in subcooled flow boiling. Part 2. Flow characteristics , 1985 .

[11]  L. S. Tong,et al.  Prediction of departure from nucleate boiling for an axially non-uniform heat flux distribution , 1967 .

[12]  J. Saini,et al.  Heat transfer in nucleate pool boiling at high heat flux , 1983 .

[13]  Steven Beyerlein,et al.  Prediction of bubble concentration profiles in vertical turbulent two-phase flow , 1985 .

[14]  A. Serizawa Theoretical prediction of maximum heat flux in power transients , 1983 .

[15]  Joel Weisman,et al.  A theoretically based critical heat flux prediction for rod bundles at PWR conditions , 1985 .

[16]  D. G. Reddy,et al.  Parametric study of CHF data. Volume 2. A generalized subchannel CHF correlation for PWR and BWR fuel assemblies. Final report , 1983 .