Coolant Flow Instabilities in Power Equipment

Regular price €254.20
A01=Vladimir Antonovich Gerliga
A01=Vladimir B. Khabensky
advanced power equipment flow stability
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Author_Vladimir Antonovich Gerliga
Author_Vladimir B. Khabensky
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Category1=Non-Fiction
Category=PBW
Category=PHDF
Category=PHDY
Category=PHH
Category=TH
Category=TQ
channel
Channel Pressure Drop
Condensate Flow Rate
Convective Heating
Coolant flow instability
Coolant Flow Rate
COP=United States
Delivery_Delivery within 10-20 working days
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eq_isMigrated=0
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experimental instability studies
Flow instability
Flow Rate Fluctuation
Flow Rate Oscillations
fluctuations
Friction Pressure
Friction Pressure Drop
generator
Heat Flux
Heat transfer
heated
Heated Channel
industrial cooling systems
Inlet Subcooling
Inlet Throttling
Language_English
Loop Flow Rate
Mass transfer
Natural Circulation Loop
nuclear thermal hydraulics
oscillatory flow modeling
PA=Available
pressure
Pressure Drop
Pressure Drop Component
Pressure Fluctuation Amplitude
Price_€100 and above
PS=Active
rate
reactor safety analysis
Single Phase Coolant
softlaunch
stability
Stability boundary
Static Stability Boundary
steam
Steam Generator
Supercritical parameters
Superheating Section
Thermal Hydraulic Characteristic
Thermal Hydraulic Parameters
Thermal-acoustic pressure fluctuations
Thermal-hydraulic instability
two-phase flow dynamics

Product details

  • ISBN 9781466567047
  • Weight: 684g
  • Dimensions: 156 x 234mm
  • Publication Date: 17 Dec 2012
  • Publisher: Taylor & Francis Inc
  • Publication City/Country: US
  • Product Form: Hardback
  • Language: English
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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.