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