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Coolant Flow Instabilities in Power Equipment [Kõva köide]

  • Formaat: Hardback, 388 pages, kõrgus x laius: 234x156 mm, kaal: 657 g, 3 Tables, black and white; 206 Illustrations, black and white
  • Ilmumisaeg: 17-Dec-2012
  • Kirjastus: CRC Press Inc
  • ISBN-10: 146656704X
  • ISBN-13: 9781466567047
Teised raamatud teemal:
  • Formaat: Hardback, 388 pages, kõrgus x laius: 234x156 mm, kaal: 657 g, 3 Tables, black and white; 206 Illustrations, black and white
  • Ilmumisaeg: 17-Dec-2012
  • Kirjastus: CRC Press Inc
  • ISBN-10: 146656704X
  • ISBN-13: 9781466567047
Teised raamatud teemal:
The authors have collected research and other literature on instability issues with coolant flow in power equipment to provide an overview of experimental and predictive investigation results that focused on thermal-hydraulic flow instabilities in equipment used in thermal and nuclear installations. It also is intended to reflect the state of the art in the field. Topics include: two-phase oscillatory thermal-hydraulic instability, oscillatory flow stability boundary, static instability, thermal-acoustic oscillations in heated channels, instability of condensing flows, and cases of flow instability in pipelines. The book would be useful for readers working in the field or related areas. Authors are Khabensky and Gerliga, for whom no background information is given. Annotation ©2013 Book News, Inc., Portland, OR (booknews.com)

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.

Foreword ix
Introduction xi
Nomenclature xv
1 Two-Phase Flow Oscillatory Thermal-Hydraulic Instability
1(50)
1.1 Classification of Types of Thermal-Hydraulic Instability and Typical Thermal and Hydrodynamic Boundary Conditions
1(4)
1.2 Two-Phase Flow Instability at Low Exit Qualities
5(17)
1.2.1 Effect of the Individual Upflow Section Height
12(3)
1.2.1.1 Throttling Effect
15(2)
1.2.1.2 Effect of Exit Quality Increase
17(1)
1.2.1.3 Effect of Coolant Flow Rate and Pressure in the System
18(1)
1.2.1.4 Effect of Heat Flux Surface Density
18(1)
1.2.1.5 Effect of Power Distribution along the Height
19(1)
1.2.1.6 Effect of Coolant Flashing in Individual Riser Section
20(1)
1.2.1.7 Effect of Nonidentical Parallel Channels
21(1)
1.3 Two-Phase Flow Oscillatory Instability at High Exit Qualities (Density-Wave Instability)
22(21)
1.3.1 Instability Mechanism
24(8)
1.3.2 Effect of Pressure
32(1)
1.3.3 Effect of Local and Distributed Hydraulic Resistance
32(3)
1.3.4 Effect of Nonheated Inlet and Exit Sections
35(1)
1.3.5 Effect of Inlet Coolant Subcooling
36(2)
1.3.6 Effect of Specific Heat Flux, Mass Velocity, Channel Length, and Equivalent Diameter
38(2)
1.3.7 Effect of Kind and Height Distribution of Heating
40(2)
1.3.8 Effect of Channel Orientation
42(1)
1.4 Simplifying Assumptions Underlying Mathematical Model and Their Effect on Accuracy of Thermal-Hydraulic Stability Boundary Prediction
43(8)
2 Oscillatory Stability Boundary in Hydrodynamic Interaction of Parallel Channels and Requirements to Simulate Unstable Processes on Test Facilities
51(22)
2.1 Qualitative Effect of Hydrodynamic Interaction of Parallel Channels on Oscillatory Stability Boundary
51(11)
2.1.1 Use of Compressible Volumes
52(3)
2.1.2 Use of Bypass
55(2)
2.1.3 Use of a System of Two Parallel Heated Channels
57(3)
2.1.4 Use of Two Hydraulically Identical Parallel Channels with Nonheated Bypass
60(1)
2.1.5 Use of Test Facilities with Multichannel Systems
61(1)
2.2 Simulation of Thermal-Hydraulic Instability in Complex Systems
62(11)
3 Simplified Correlations for Determining the Two-Phase Flow Thermal-Hydraulic Oscillatory Stability Boundary
73(26)
3.1 Introduction
73(1)
3.2 The CKTI Method
74(2)
3.3 The Saha-Zuber Method
76(6)
3.4 The Method of the Institute for Physics and Energetics (IPE)
82(7)
3.5 Determination of Oscillatory Stability Boundary at Supercritical Pressures
89(10)
3.5.1 The CKTI Method
94(2)
3.5.2 The Saha-Zuber Method
96(3)
4 Some Notes on the Oscillatory Flow Stability Boundary
99(46)
4.1 Introduction
99(1)
4.2 Experimental Determination of the Stability Boundary
100(8)
4.3 Experimental Determination of Thermal-Hydraulic Stability Boundaries of a Flow Using Operating Parameter Noise
108(7)
4.4 The First Approximation Stability Investigation
115(7)
4.5 Stability Investigations Based on Direct Numerical Solution of the Unsteady System of Nonlinear Equations
122(22)
4.5.1 Construction of the Discrete Analog of the Initial System of Differential Equations
131(13)
4.6 Conclusion
144(1)
5 Static Instability
145(84)
5.1 Basic Definitions
145(8)
5.2 Ambiguity of Hydraulic Curve due to Appearance of a Boiling Section at the Heated Channel Exit
153(8)
5.2.1 Effect of Local Hydraulic Resistance
155(2)
5.2.2 Pressure Effect
157(1)
5.2.3 Effect of Channel Inlet Coolant Subcooling
157(1)
5.2.4 Effect of Heat Flux Density, Channel Length, and Equivalent Diameter
158(2)
5.2.5 Effect of Heating Distribution and Kind
160(1)
5.2.6 Effect of the Pressure Drop Gravity Component and Steam Slip Coefficient
160(1)
5.3 Hydraulic Characteristic Ambiguity in the Presence of a Superheating Section
161(21)
5.3.1 Specifics of the Ambiguity Region Formation
161(2)
5.3.2 Effect of the Kind of Heating
163(9)
5.3.3 Influence of Parallel-Channel Operation and Means of Controlling Parameters
172(5)
5.3.4 The Ballast Zone
177(5)
5.4 Hydraulic Characteristic Ambiguity in Cases of Coolant Downflow and Upflow-Downflow
182(29)
5.4.1 Two-Phase Coolant Flow Static Instability
184(2)
5.4.1.1 Effect of the Channel Heated Height
186(1)
5.4.1.2 Effect of Channel Equivalent Diameter
187(1)
5.4.1.3 Effect of Pressure
188(1)
5.4.1.4 Effect of Heat Flux Surface Density
188(2)
5.4.1.5 Effect of Heat Flux Nonuniformity along the Height
190(1)
5.4.1.6 Effect of Heating Surfaces' Arrangement in Channels with Coolant Upflow-Downflow
191(2)
5.4.1.7 Effect of Throttling
193(1)
5.4.1.8 Effect of Steam Slip
194(1)
5.4.1.9 Effect of Channel Inlet Coolant Subcooling
194(7)
5.4.2 Single-Phase Coolant Flow Static Instability
201(10)
5.5 Pressure Drop Oscillations
211(15)
5.6 Some Other Mechanisms Inducing Static Instability
226(3)
6 Thermal-Acoustic Oscillations in Heated Channels
229(42)
6.1 Thermal-Acoustic Oscillations at Subcritical Pressures
229(22)
6.1.1 Oscillations' Development Pattern and Initiation Mechanism
229(10)
6.1.2 Effect of Flow Parameters on Oscillation Characteristics
239(12)
6.2 TAOs at Supercritical Pressures
251(20)
6.2.1 Oscillations' Development Pattern: A Concept of Oscillations' Initiation Mechanism
251(6)
6.2.2 Effect of Flow Parameters on Oscillation Characteristics at Supercritical Pressures
257(3)
6.2.3 Effect of Channel Design Specifics on Heat Removal and TAOs' Characteristics
260(6)
6.2.4 Effect of Dissolved Gas on TAOs' Characteristics
266(5)
7 Instability of Condensing Flows
271(20)
7.1 Introduction
271(3)
7.2 Instability of Condenser Tube and Hotwell System
274(3)
7.3 Interchannel Instability in System of Parallel-Connected Condensing Tubes
277(11)
7.4 Water Hammers in Horizontal and Almost Horizontal Steam and Subcooled Water Tubes
288(1)
7.5 Instability of Bubbling Condensers
289(2)
8 Some Cases of Flow Instability in Pipelines
291(50)
8.1 Self-Oscillations in Inlet Line-Pump System
291(14)
8.2 Instability of Condensate Line-Deaerator System
305(9)
8.3 Vibration of Pipelines with Two-Phase Adiabatic Flows
314(17)
8.3.1 Examples of Vibration of Industrial Pipelines with Two-Phase Flows
314(5)
8.3.2 Vibration of Gas-Liquid Pipelines
319(1)
8.3.2.1 Pulsations of the Adiabatic Two-Phase Flow Pressure in Pipelines
319(7)
8.3.2.2 Transport Delay-Based Instability Mechanism
326(3)
8.3.2.3 Hysteresis of the Hydraulic Discriminant in Pipelines
329(1)
8.3.2.4 Slug and Plug Regimes of the Two-Phase Flow in Pipelines
330(1)
8.3.2.5 Oscillatory Processes in the Two-Phase Flow in the Externally Controlled Pipelines
330(1)
8.4 Two-Phase Flow Instabilities and Bubbling
331(10)
References 341(12)
Index 353
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.