Convective Flow Boiling

ISBN-13: 9780367455934 / Angielski / Miękka / 2019 / 304 str.

John C. Chen

Opis

This book comprises selected papers from the First International Conference on Convective Flow Boiling. The purpose of the conference is to examine state-of-science and recent developments in technology of flow boiling, i.e., boiling systems which are affected by convective flows.

Spis treści

Phenomenlogical issues in forced convective boiling; critical heat flux mechanisms; vapor bubble growth in highly subcooled heterogeneous boiling; void fraction and recondensation rate in subcooled forced convective boiling with Freon R12; convective flow boiling in coiled tubes; heat transfer and pressure drop characteristics of forced convective evaporation in deep spirally fluted tubing; the physical dimension in convective boiling; contributors of convection and boiling to convective flow boiling an alternative model for flow boiling heat transfer; effect of wall thermal conditions on cross flow film boiling heat transfer; flow boiling in bubbly flow; flow boiling in a narrow channel; heat transfer in a subcooled falling liquid film; modeling of hydrodynamic parameters and CHF in spray cooling (part contents.

O autorze

John C. Chen currently holds the Carl R.Anderson Chair of Chemical Engineering at Lehigh University, where he has also served as Chairman of the Department of Chemical Engineering and as Director of the Institute of Thermo-Fluid Engineering and Science. His research encompasses both vapor-liquid and particle-gas multiphase systems., Yasunobu Fujita is currently Professor of Energy and Mechanical Engineering at Kyushu University, Japan. His research concentrates on mechanistic aspects of nucleate boiling, high density cooling, CHF of binary mixtures, and direct contact evaporation., Franz Mayinger holds the prestigious Chair of Thermodynamik at Technische Universität Munich, Germany. His research on boiling and condensation is characterized by innovative and meticulous experimental investigations which contributed to the understanding of many of the significant mechanisms., Ralph A. Nelson is a Senior Research Scientist at Los Alamos National Laboratory, New Mexico and is considered a world leader in the development of transient two-phase computer codes for thermal-hydraulic analysis of nuclear reactor systems.