Thermal-hydraulic instability can potentially impair thermal reliability of reactor cores or other power equipment components. Thus it is important to address stability issues in power equipment associated with thermal and nuclear installations, particularly in thermal nuclear power plants, chemical and petroleum industries, space technology, and radio, electronic, and computer cooling systems. Coolant Flow Instabilities in Power Equipment synthesizes results from instability investigations around the world, presenting an analysis and generalization of the published technical literature.
The authors include individual examples on flow stability in various types of equipment, including boilers, reactors, steam generators, condensers, heat exchangers, turbines, pumps, deaerators, bubblers, and pipelines. They also present information that has not been widely available until recently, such as thermal-acoustic instability, flow instability with supercritical parameters, and single-phase coolant flow static instability. The material described in this book is derived from vast amounts of experimental data from thermal-physical test facilities and full-scale installations. It is presented in a manner accessible to readers without advanced mathematical backgrounds.
Particular attention has been paid to oscillatory (low-frequency and thermal-acoustic) and static thermal-hydraulic coolant flow instability. In addition, the physical mechanism of instability has been considered in detail. This book provides knowledge of the various types of flow instability, the equipment where this instability can manifest, and the ensuing consequences, as well as makes recommendations concerning possible removal or mitigation of these consequences. The authors provide this information as a useful reference for readers to facilitate the enhanced safety of modern power equipment through qualitative evaluation of design and flow parameters and subsequent selection of the optimal means for increasing flow stability.
Professor Vladimir B. Khabensky is the leading scholar in the field of heat transfer and hydrodynamics of the single- and double-phase flows in thermal and nuclear power engineering. He has been celebrated for his contribution to mathematical modeling of nonstationary thermo-hydraulic processes in NPP. More recently, he has contributed greatly to understanding of physicochemical and thermo-hydraulic processes in the high-temperature molten corium in the context of the problem of NPP safety during a severe accident involving the core meltdown. He has authored over 160 research manuscripts and inventions.
Professor Vladimir A. Gerliga
is renowned for his contribution to the field of nuclear power plant safety, hydraulic gas dynamics, pumps, turbines, and power installations of space vehicles. His research focused on physical and mathematical models of thermo-acoustic fluctuations in the channel core of nuclear power plants and designing methods for instability prediction in the main circuit on natural circulation by the analysis of noise. He has authored 5 books and over 150 research manuscripts.
