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This book offers an analysis and generalization of various thermal-hydraulic coolant flow instabilities that occur in power equipment components of thermal and nuclear stations and have been reported in the published technical literature. The authors examine numerous examples of instability expression in a range of equipment including boilers, reactors, steam generators, condensers, heat exchangers, turbines, pumps, deaerators, bubblers, and pipelines. In addition to the traditional sections, the book includes material that, until recently, has not been reflected in monographs and education literature.…mehr

Produktbeschreibung
This book offers an analysis and generalization of various thermal-hydraulic coolant flow instabilities that occur in power equipment components of thermal and nuclear stations and have been reported in the published technical literature. The authors examine numerous examples of instability expression in a range of equipment including boilers, reactors, steam generators, condensers, heat exchangers, turbines, pumps, deaerators, bubblers, and pipelines. In addition to the traditional sections, the book includes material that, until recently, has not been reflected in monographs and education literature.

Dieser Download kann aus rechtlichen Gründen nur mit Rechnungsadresse in A, B, BG, CY, CZ, D, DK, EW, E, FIN, F, GR, HR, H, IRL, I, LT, L, LR, M, NL, PL, P, R, S, SLO, SK ausgeliefert werden.

Autorenporträt
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.