Nuclear reactor thermal hydraulics: an introduction to nuclear heat transfer and fluid flow

✍ Scribed by Masterson, Robert

• Publisher: CRC Press
• Year: 2020
• Tongue: English
• Leaves: 1391
• Category: Library

✦ Synopsis

"Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considertions. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students. A complete Solutions Manual is available for professors adopting the text"--;Nuclear power in the world today -- The pressurized water reactor -- The boiling water reactor -- Fast reactors, gas reactors, and military reactors -- Thermal energy production in nuclear power plants -- The laws of thermodynamics -- Thermodynamic properties and equations of state -- The nuclear steam supply system -- Reactor thermal cycles -- The laws of heat transfer -- Heat removal from nuclear fuel rods -- Time dependent nuclear heat transfer -- Nuclear reactor fluid mechanics -- Fluid statics and fluid dynamics -- The conservation equations of fluid mechanics -- Single phase flow in nuclear power plants -- Laminar and turbulent flow with friction -- Core and fuel assembly fluid flow -- Reactor coolants, coolant pumps, and power turbines -- Single phase nuclear heat transfer -- Correlations for single phase nuclear heat transfer -- Natural convection in nuclear power plants -- Fundamentals of two phase flow in nuclear power plants -- Two phase nuclear heat transfer -- Heat transfer correlations for advanced two phase nuclear heat transfer -- Core temperature fields -- Nuclear hot channel factors, the critical heat flux, and the dnbr -- Thermal design limits, operating limits, and safety limits -- Equilibrium and non-equilibrium flows, critical flow, and choke flow -- Reactor accidents, dbas, and locas -- Flow oscillations, density waves, and hydrodynamic instabilities -- Containment buildings and their function -- particle transport and entrainment during reactor accidents -- Response of a containment building to a reactor LOCA.

✦ Table of Contents

Cover......Page 1
IFC......Page 2
Half Title......Page 3
Title Page......Page 5
Copyright Page......Page 6
Contents......Page 7
Preface......Page 27
An Overview of the Book......Page 29
Author......Page 35
1.2 Number of Power Reactors around the World......Page 37
1.3 Power Reactor Architectures......Page 40
1.5 Schematic of a Nuclear Power Plant......Page 42
1.6 Coolants Used in Nuclear Power Plants......Page 44
1.7 Types of Nuclear Fuel......Page 46
1.8 Properties of Nuclear Fuel......Page 48
1.9 Reactor Pressure Vessels and Their Properties......Page 49
1.11 Characteristics of Reactor Fuel Assemblies......Page 51
1.12 Other Important Reactor Properties (Power Density and Thermal Efficiency)......Page 53
1.13 The Power Density......Page 54
1.14 Thermal Efficiency......Page 55
1.15 Control Rods and Their Function......Page 57
1.16 Comparing PWR Control Rods and BWR Control Rods......Page 58
1.17 Use of the Scram Button and the Word SCRAM......Page 60
1.20 SGs and Their Uses......Page 61
1.22 SG and Steam Turbine Pairing......Page 62
1.23 Electrical Generators in Nuclear Power Plants......Page 63
1.24 Common Measurements of Electrical Power Production......Page 65
1.25 Nikola Tesla and Thomas Edison and Their Contributions to the Field of Nuclear Power......Page 66
1.26 The Relationship between Nikola Tesla and George Westinghouse......Page 68
Books and Textbooks......Page 69
Questions for the Student......Page 70
Exercises for the Student......Page 71
2.2 PWR Cores and Pressure Vessels......Page 73
2.4 Flow Paths through the Pressure Vessel and the Core......Page 75
2.5 Steam Generators......Page 76
2.6 Steam Generator Characteristics and Their Internal Geometries......Page 78
2.7 Reactor Coolant Pumps......Page 79
2.8 The Pressurizer......Page 81
2.9 Fuel Assemblies for PWRs......Page 83
2.10 VVER Reactors and Russian PWRs......Page 85
2.11 Canadian Pressurized Heavy Water Reactors (CANDU Reactors)......Page 86
2.12 Fuel Assemblies for PHWRs (CANDU Reactors)......Page 88
2.14 Temperature Profiles in a PWR Core......Page 91
2.15 Movement to Standard Reactor Designs......Page 92
2.16.1 The Trend toward Passive Safety Systems......Page 93
2.17 Characteristics of PWRs......Page 94
2.18 Core Characteristics and Design Parameters......Page 95
2.19 Understanding How the Passive Cooling System Works in the Westinghouse AP-1000......Page 96
2.20 Boric Acid in PWRs......Page 100
Questions for the Student......Page 102
Exercises for the Student......Page 103
3.1 Boiling Water Reactors......Page 105
3.2 Types of American BWRs......Page 106
3.3 Fuel Assemblies for BWRs......Page 108
3.5.1 RBMK Design Parameters......Page 110
3.6 Temperature Profiles in a Typical BWR Core......Page 112
3.7 The Advanced BWR and the Simplified BWR......Page 114
3.8 The Simplified BWR......Page 115
3.10 Core Characteristics and Design Parameters......Page 116
3.12 Finding the Density from the Void Fraction......Page 117
3.13 The Relationship between the Void Fraction and the Quality......Page 119
3.14 BWR Flow Regimes......Page 121
3.16 BWR Operating Maps......Page 124
3.17 Lessons That Can Be Learned from a Reactor Operating Map......Page 125
Books and Textbooks......Page 127
Questions for the Student......Page 128
Exercises for the Student......Page 129
4.3 Fast Reactor Coolants......Page 131
4.4 Advanced Gas Reactors......Page 132
4.5 Liquid Metal Fast Breeder Reactors......Page 133
4.6 Fuel Assemblies for LMFBRs......Page 135
4.8 Other Reactor Concepts......Page 138
4.9 Military Reactors and the MPR......Page 140
4.11 HTGR Fuel......Page 142
4.12 Comparing the Designs of Gas Reactors......Page 143
4.13 Gas Reactor Cores and Design Parameters......Page 146
4.14 LMFBR Thermal Cycle Performance......Page 147
4.15 Characteristics of LMFBR Cores......Page 148
4.16 Comparing the Power Densities in Different Reactor Cores......Page 149
4.17 The NSSS and the Containment Building for Fast Reactors......Page 150
4.18 Theoretical Thermal Efficiencies......Page 151
4.19 Earliest Fast Reactors......Page 152
Questions for the Student......Page 153
Exercises for the Student......Page 155
5.2 Measuring Nuclear Energy......Page 157
5.4 Cross Sections and Reaction Rates......Page 158
5.5 Converting the Kinetic Energy of Nuclear Particles into Thermal Energy......Page 161
5.6 Energy Produced by the Fission Process......Page 162
5.7 Estimating the Total Energy Release......Page 163
5.8 Other Types of Nuclear Particles and Radiation......Page 164
5.10 Radioactive Decay Heat......Page 165
5.11 Attenuation Coefficients for Different Types of Nuclear Radiation......Page 166
5.12 Energy of Fission Neutrons......Page 167
5.13 The Maxwell–Boltzmann Probability Distribution......Page 170
5.14 Thermal Energy Produced in Nuclear Fuel Rods......Page 171
5.15 The Fuel Rod Cladding......Page 173
5.17 PWR, BWR, and LMFBR Fuel Assemblies......Page 175
5.20 Fuel Rods in Hexagonal Fuel Assemblies......Page 177
5.21 CANDU Reactor Fuel Assemblies......Page 179
5.22 Where Nuclear Energy Is Produced in the Core......Page 180
5.23 Ways of Measuring the Core Power......Page 181
5.24 Heat Generation in Nuclear Fuel Assemblies......Page 183
5.25 The Volumetric Power Densities for Different Reactor Types......Page 185
5.27 Power Profiles in Reactor Fuel Assemblies......Page 186
5.28 Using Burnable Poisons to Flatten the Power and Temperature Profile......Page 188
5.29 Axial Power Shapes and Power Peaks......Page 189
5.30 Using Axial Zoning to Reduce Power Peaks......Page 190
5.32 Neutron Reflectors......Page 191
5.33 Axial Power Profiles in Uniform, Unreflected Cores......Page 192
5.34 Radial Power Profiles in Uniform, Unreflected Cores......Page 193
5.36 Extrapolated Power Profiles......Page 194
5.37 Global Power Profiles in Different Types of Cores......Page 197
5.40 Flattening the Power Profile......Page 198
5.41 How Control Rods Affect the Core-Wide Power Profile......Page 199
5.42 Power Fluctuations in Steady-State Cores......Page 201
5.46 Decay Heat from Beta Decay......Page 203
5.47 Cherenkov Radiation......Page 204
5.49 Removing Decay Heat from the Core......Page 205
5.50 Decay Heat Removal after Shutdown......Page 207
5.51 ANS Standards Governing Decay Heat......Page 209
Web References......Page 210
Questions for the Student......Page 211
Exercises for the Student......Page 213
6.2 The First Law of Thermodynamics......Page 215
6.3 Understanding Energy Transfer in Nuclear Systems......Page 217
6.4.2 Heat Transfer......Page 218
6.5 Generalized Energy Transfer......Page 219
6.6 Heat Energy and the First Law of Thermodynamics......Page 220
6.8 The Second Law of Thermodynamics......Page 221
6.9 Alternative Statements of the Second Law......Page 222
6.10 The Clausius Inequality......Page 223
6.11 The Increase in Entropy Principle......Page 224
6.12 The Third Law of Thermodynamics......Page 225
6.13 The Fourth or the Zeroth Law of Thermodynamics......Page 226
6.14 Understanding the Difference between Thermodynamics and Heat Transfer......Page 227
6.17 Defining a Pure Material or Substance......Page 228
6.20 Nuclear Temperature Scales......Page 229
6.22 The Definition of Energy......Page 231
6.23 The Definition of Work......Page 233
6.25 The Definition of Power......Page 234
6.27 The Units of Pressure......Page 235
6.29 Using Thermodynamic State Variables......Page 237
6.30 Understanding the Internal Energy and the Enthalpy......Page 238
6.31 Finding the Enthalpy When a Material Changes Phase......Page 239
6.33 The Temperature Behavior of Single- Phase Flows and Two-Phase Mixtures......Page 243
6.35 The Clausius–Clapeyron Equation......Page 245
6.36 The Relationship between the Pressure and the Boiling Point of Water in Light Water Reactors......Page 246
6.38 Pressure–Temperature Diagrams and Phase Diagrams......Page 247
6.39 Temperature–Volume Diagrams......Page 249
6.41 Heat Engines......Page 250
6.42 The Carnot Thermal Cycle......Page 251
6.43 Thermal Efficiencies of Nuclear Power Plants......Page 252
Books and Textbooks......Page 253
Questions for the Student......Page 254
Exercises for the Student......Page 255
7.1 Thermodynamic Properties and Nuclear Power Plants......Page 257
7.4 Thermodynamic Equations of State......Page 258
7.5 The Equation of State for the Ideal Gas Law......Page 259
7.6 Treating Steam as an Ideal Gas......Page 260
7.8 Other Equations of State......Page 261
7.9 Inferring the Behavior of Reactor Coolants from Other State Variables......Page 262
7.10 Defining the Enthalpy and Specific Enthalpy of a Fluid......Page 263
7.11 Finding the Enthalpy of a Two-Phase Mixture......Page 264
7.12 Phase Changes in Reactor Coolants......Page 265
7.14 Using Property Diagrams to Describe Phase Changes......Page 266
7.16 Temperature–Volume Diagrams......Page 268
7.17 Pressure–Volume Diagrams......Page 269
7.20 Determining the Boiling Point from Clausius–Clapeyron Equation......Page 270
7.22 The Quality of a Two-Phase Mixture......Page 271
7.23 Using the Quality to Define the Properties of a Two-Phase Mixture......Page 272
7.24 Relationships between the Quality and the Void Fraction......Page 273
7.26 The Steam Tables......Page 275
7.27 Thermodynamic Properties of Water and Steam......Page 276
7.28 The Behavior of Air–Water Mixtures......Page 281
7.31 Thermodynamic Cycles and Path Functions......Page 283
7.32 The Relationship between the Path a System Takes, and Its Heat and Work Output......Page 285
7.33 Deriving Work from a State Diagram......Page 286
7.34 Finding the Thermal Efficiency from a T–S Diagram......Page 287
7.36 Definitions of the Specific Heats......Page 290
7.39 The Specific Heat for a Pure Substance......Page 291
7.40 The Specific Heat for an Ideal Gas......Page 293
7.41 Other Ways to Find the Specific Heat......Page 294
7.44 Applying Specific Heats to Reactor Coolant Pumps......Page 296
7.45 Calculating the Heat Transfer Rate Using the Specific Heats......Page 297
7.46 Determining the Coolant Temperature Profiles in a PWR......Page 298
7.47 Performing an Energy Balance Using the Enthalpy in a Reactor Heat Exchanger......Page 299
Books and Textbooks......Page 300
Questions for the Student......Page 301
Exercises for the Student......Page 302
8.1 The Nuclear Steam Supply System......Page 305
8.2 Understanding the NSSS......Page 306
8.3 The Components of the NSSS......Page 308
8.4 Thermal Efficiency Optimization......Page 310
8.6 Reactor Steam Generators......Page 311
8.7 Types of Reactor SGs......Page 313
8.9 More on Reactor SGs......Page 315
8.10 SGs and Heat Exchangers......Page 317
8.11 Steam Turbines......Page 318
8.13 SG and Steam Turbine Pairings......Page 319
8.15 How an Electric Generator Works......Page 320
8.16 Condensers and Other Heat Rejection Devices......Page 323
8.17 The Demineralizer......Page 324
8.19 Types of Reactor Cooling Towers......Page 325
8.20 Heat Transfer through a Reactor Cooling Tower......Page 327
8.21 Types of Heat Exchangers......Page 329
8.22 Heat Exchanger Design......Page 331
8.23 Finding the Heat Transfer Rate through a Heat Exchanger Tube......Page 333
8.25 Assumptions Regarding the LMTD......Page 336
8.27 Practical Applications of the LMTD......Page 338
8.29 Accounting for Crud Buildup in Heat Exchanger Tubes......Page 340
8.30 Tube Fouling Factors......Page 341
8.32 Fluid Properties and Their Effect on Thermal Efficiency......Page 343
Books and Textbooks......Page 345
Questions for the Student......Page 346
Exercises for the Student......Page 347
9.1 The Purpose of Reactor Thermal Cycles......Page 349
9.2 An Introduction to the Rankine Thermal Cycle......Page 350
9.3 The Steps in the Rankine Thermal Cycle......Page 351
9.5 An Energy Balance through the NSSS......Page 354
9.6 Improving the Performance of an Ideal Rankine Cycle......Page 356
9.7 Method 1: Superheating the Steam......Page 357
9.8 Other Efficiency Improvements— Reheat and Regeneration......Page 358
9.9 Method 2: Reheating the Steam......Page 359
9.10 Method 3: Regenerating the Cooling Water......Page 361
9.11 Thermodynamic Analysis of Regeneration......Page 362
9.13 Some Additional Facts Regarding Regeneration......Page 366
9.14 Reducing the Condenser Temperature and Pressure......Page 367
9.16 Balancing the Energy Flow between the Primary and Secondary Loops in a PWR......Page 368
9.17 Estimating the Work a Steam Turbine Performs......Page 370
9.18 Using Condensers to Reject Waste Heat......Page 371
9.19 Comparing Turbine Work and Pump Work......Page 372
9.20 Open-Loop Thermal Cycles......Page 374
9.21 Removing the Waste Heat from a Nuclear Power Plant......Page 375
9.22 Differences between an Actual Rankine Cycle and an Idealized One......Page 376
9.24 The Four Steps in an Ideal Brayton Cycle......Page 377
9.25 Hybrid Thermal Cycles for Gas-Cooled Reactors......Page 380
9.26 Fast Reactor Thermal Cycles......Page 381
9.27 Moving On......Page 383
Questions for the Student......Page 384
Exercises for the Student......Page 385
10.2 Comparing Conduction, Convection, and Radiation......Page 387
10.3 Conductive Heat Transfer and Fourier’s Law of Conduction......Page 390
10.4 The Assumptions Used in Fourier’s Law of Conduction......Page 391
10.5 Newton ’s Law of Cooling......Page 392
10.6 The Thermal Conductivity and Wiedemann–Franz Law......Page 393
10.7 The Specific Heat and the Heat Capacity......Page 396
10.8 Newton’s Law of Convection......Page 397
10.9 The Nusselt Number for Convective Heat Transfer......Page 398
10.10 Radiative Heat Transfer and the Greenhouse Effect......Page 399
10.11 The Stefan–Boltzmann Law......Page 401
10.12 Energy Deposition due to Radiation in a Reactor Core......Page 403
10.13 Heat Deposited by Gamma Rays......Page 405
10.15 Cooling Spent Nuclear Fuel......Page 406
10.18 The Thermal Resistance......Page 408
10.19 The Thermal Resistance and Its Applications......Page 409
10.20 The Thermal Resistance of an Object in a Radiation Field......Page 411
10.21 Heat Flow through Multilayered Objects......Page 412
10.22 Composite Thermal Resistances......Page 413
10.23 The Thermal Contact Resistance......Page 414
10.25 Heat Conduction in Cylindrical and Spherical Objects......Page 415
10.26 Finding the Thermal Resistance of the Cladding and the Coolant......Page 417
10.27 Treating a Nuclear Fuel Rod as a Serial Heat Conduction Problem......Page 418
10.28 An Introduction to Parallel Heat Transfer......Page 420
10.29 Problems with both Serial and Parallel Heat Transfer......Page 421
10.30 Heat Conduction in Nuclear Fuel Rods......Page 422
10.31 Heat Conduction in Fuel Rods with a Fuel–Cladding Gap......Page 423
10.33 Finding the Heat Transfer Rate When the Thermal Conductivity Is a Function of Temperature......Page 425
10.34 Summarizing Our Findings......Page 426
10.35 Typical Values of the Nuclear Heat Flux and the Fuel Rod Temperature......Page 428
10.38 Problems with Conduction, Convection, and Radiative Heat Transfer......Page 429
Questions for the Student......Page 431
Exercises for the Student......Page 433
11.2 Fourier’s Law and Its Application to Nuclear Systems......Page 435
11.4 Deriving the Heat Conduction Equation......Page 437
11.5 Deriving of the Time-Dependent Heat Conduction Equation......Page 439
11.7 The Form of the Heat Conduction Equation in Different Coordinate Systems......Page 441
11.9 Other Ways to Classify the Heat Conduction Equations......Page 443
11.10 A Brief Review of Nuclear Fuel Rods and Their Properties......Page 444
11.11 Fuel Rod Thermal Properties......Page 445
11.12 The Power Output of the Fuel and the Core......Page 447
11.13 Comparing the Temperature Drops in BWR and PWR Fuel Rods......Page 448
11.15 Implementing Different Types of Boundary Conditions......Page 449
11.16 Solutions to the Steady-State Heat Conduction Equation for Plate-Type Fuel Rods......Page 451
11.17 The Temperature Profile of a Fuel Pin in a Plate-Type Fuel Rod......Page 452
11.18 The Temperature Profile for the Cladding in a Plate-Type Fuel Rod......Page 453
11.19 The Thermal Resistance of a Plate-Type Fuel Rod......Page 454
11.20 Solutions to the Steady-State Heat Conduction Equation for Cylindrical Fuel Rods......Page 455
11.21 The Temperature Profile of the Fuel in a Cylindrical Fuel Rod......Page 456
11.22 The Temperature Profile of the Cladding in a Cylindrical Fuel Rod......Page 457
11.23 The Thermal Resistance of a Cylindrical Fuel Rod......Page 458
11.24 Comparing the Thermal Resistance Terms in a Plate-Type Fuel Rod and in a Cylindrical Fuel Rod......Page 460
11.25 Understanding the Physical Restructuring of Nuclear Fuel......Page 461
11.26 Solutions to the Steady-State Heat Conduction Equation for a Cylindrical Fuel Rod with a Central Hole or Void......Page 462
11.27 How the Thermal Conductivity of Uranium Dioxide Changes with Temperature and Burnup......Page 464
11.28 The Effects of Operation and Irradiation on a Nuclear Fuel Rod......Page 465
11.29 Fission Gas Release in a Nuclear Fuel Rod......Page 466
11.30 Accounting for Density Changes in the Fuel......Page 467
11.31 Adding a Gap to a Fuel Rod......Page 468
11.32 Finding the Gap Temperature Drop......Page 469
11.33 Finding the Cladding Temperature Drop......Page 471
11.35 Finding the Temperature Drop across an Irradiated Fuel Pin......Page 473
11.37 Comparing the Average Fuel Pin Temperatures in Solid and Annular Pins......Page 475
11.38 An Overview of the Temperature Drop across a Nuclear Fuel Rod......Page 477
11.39 Finding the Operating Temperature of a Typical Nuclear Fuel Rod......Page 478
11.40 The Effects of Gap Closure and Parallel Conduction on the Gap Heat Transfer Coefficient......Page 479
11.41 The Advantages of Annular Fuel Rods......Page 484
11.42 Fuel Rods with Axially Dependent Heat Generation Rates......Page 488
11.43 Temperature Profiles in Objects with Exponential Heat Sources......Page 489
11.44 Future Trends in Fuel Rod Design and Conductive Heat Transfer......Page 491
Books and Textbooks......Page 492
Questions for the Student......Page 493
Exercises for the Student......Page 495
12.2 Boundary Conditions and Fourier’s Equation......Page 497
12.5 Time-Dependent Heat Transfer in Nuclear Fuel Rods......Page 498
12.6 The Temperature Profile during a Rapid Power Increase......Page 499
12.7 Fuel Pin Power Decreases......Page 500
12.8 Understanding the Time-Dependent Heat Transfer Equation......Page 501
12.9 Fourier’s Equation for Conductive Heat Transfer......Page 502
12.10 Solutions to Fourier’s Equation for Some Simple Reactor Geometries......Page 503
12.11 The Biot Number and the Fourier Number......Page 505
12.12 The Time Constant for Nuclear Heat Transfer......Page 506
12.13 Higher Order Solutions to Fourier’s Equation......Page 507
12.14 Time-Dependent Temperature Profiles in Large Reactor Components......Page 508
12.16 Finding the Biot Number......Page 512
12.17 Estimating the Centerline Temperatures in Homogeneous Objects......Page 513
12.18 The Physical Significance of the Biot Number......Page 514
12.19 Transient Heat Conduction for Multidimensional Shapes......Page 515
Books and Textbooks......Page 517
Questions for the Student......Page 518
Exercises for the Student......Page 519
13.2 Internal Flows with and without Friction......Page 521
13.6 Laminar and Turbulent Flows......Page 524
13.7 Forced and Unforced Flows......Page 525
13.8 Steady and Unsteady Flows......Page 526
13.9 Developed and Undeveloped Flows......Page 528
13.11 Classifying Reactor Coolant Flows......Page 529
13.12 Reducing the Conservatism in Reactor Fluid Mechanics Calculation s......Page 530
13.13 Using Control Volumes in Reactor Fluid Mechanics......Page 531
13.14 Using a Lumped Parameter Approach......Page 532
13.16 The State Postulate......Page 533
13.18 Definition of the Vapor Pressure......Page 534
13.20 Partial Pressures and the Vapor Pressure......Page 535
13.21 Coefficient of Compressibility......Page 537
13.23 Understanding Water Hammers......Page 539
13.24 Volume Changes with Temperature and Pressure......Page 540
13.25 Natural Convection Driven by Temperature and Volume Changes......Page 542
13.26 Viscosities of Common Gases and the Sutherland Correlation......Page 543
13.28 Taking Another Look at the Dynamic and Kinematic Viscosities......Page 544
13.30 Surface Wetting......Page 545
Books and Textbooks......Page 547
Questions for the Student......Page 548
Exercises for the Student......Page 549
14.1 Static Behavior of Fluids......Page 551
14.3 Pressure in Horizontal Planes......Page 552
14.4 Pascal’s Law of Pressure......Page 554
14.5 Measuring the Pressure Level in a Tank, a Pipe, or a Reactor Pressure Vessel......Page 555
14.6 Understanding Fluid Pressures in Reactor Fuel Assemblies......Page 556
14.7 Pressures for Layered Fluids......Page 557
14.8 Measuring the Pressure Drop in a Horizontal Pipe with a Monometer......Page 558
14.10 Pressure Equalization between Reactor Fuel Assemblies......Page 560
14.13 Pressure Behavior in PWRs......Page 562
14.15 Typical Pressure Levels in the Nuclear Steam Supply System......Page 564
14.17 Fluid Kinematics and Fluid Dynamics......Page 567
14.18 The Lagrangian and Eulerian Views of Fluid Mechanics......Page 568
14.20 Understanding the Differences between Advection, Diffusion, and Convection......Page 569
14.21 Finding the Acceleration of a Fluid in an Eulerian Reference Frame......Page 570
14.23 Some Observations Regarding the Advective Derivative......Page 572
14.24 The Material Derivative in Eulerian Fluid Mechanics......Page 573
14.26 Connecting the Lagrangian and the Eulerian Descriptions of Fluid Mechanics......Page 574
14.27 Rotational Flows......Page 575
14.28 The Vorticity of a Rotational Flow......Page 578
14.29 Fluid Deformation and Volumetric Strain......Page 581
14.32 Definition of a Path Line......Page 582
14.33 Definition of a Streak Line......Page 583
14.34 Definition of a Streamline......Page 584
14.36 Methods for Observing Path Lines and Streak Lines......Page 586
Books and Textbooks......Page 587
Questions for the Student......Page 588
Exercises for the Student......Page 589
15.1 The Material Derivative......Page 591
15.3 Simplifications to the Fluid Conservation Equations......Page 592
15.7 Types of Fluid Flow......Page 593
15.8 Fluid Viscosity and Friction......Page 594
15.10 Singular Solutions to the Navier–Stokes Equations......Page 597
15.11 The Fluid Conservation Equations in Different Coordinate Systems......Page 599
15.12 The Conservation Equations for One-Dimensional Flows......Page 600
15.13 Thermal-Hydraulic Correlations and Their Uses......Page 602
15.14 The Continuity Equation......Page 603
15.15 Working with the Continuity Equation......Page 605
15.16 The Energy Equation......Page 606
15.17 Working with the Fluid Energy Equation......Page 608
15.18 The Momentum Equations......Page 609
15.19 The Differential Momentum Equations......Page 611
15.20 Understanding the Advection of Momentum......Page 613
15.21 The Time-Dependent Momentum Equations......Page 614
15.22 Finding the Pressure Field from the Velocity Field......Page 616
15.23 The Navier–Stokes Equations in Cylindrical Coordinates......Page 617
15.25 Treatment of Fluid Friction in a Compressible Fluid......Page 619
15.26 Cauchy’s Equations for a Compressible Fluid......Page 620
15.27 Simplifying Cauchy’s Equations to Handle Incompressible Newtonian Fluids......Page 621
15.28 A Practical Approach to Fluid Friction in Nuclear Power Plant s......Page 622
15.30 Euler’s Equation and Its Origins......Page 624
15.31 Boundary-Layer Approximations......Page 625
15.32 Converting Euler’s Equation into Bernoulli’s Equation......Page 627
15.35 Velocity Fluctuations in Turbulent Flows......Page 628
15.37 Solving the Navier–Stokes Equations for Turbulent Flows......Page 630
15.39 Approximate Solutions to the Navier–Stokes Equations......Page 631
15.41 Fluid Boundary Conditions......Page 632
15.43 The Interface Boundary Condition......Page 633
15.46 Pressure Boundary Conditions......Page 634
15.47 Flow Boundary Conditions......Page 635
15.48 Boundary-Layer Flow......Page 636
15.49 Boundary-Layer Solutions......Page 637
15.50 Transition Points in Boundary-Layer Theory......Page 638
15.51 Fluid Mechanical Modeling of a Reactor Core......Page 639
15.52 Reviewing What We Have Just Learned......Page 640
Questions for the Student......Page 641
Exercises for the Student......Page 643
16.1 Single-Phase Flow......Page 645
16.2 Using Gases as Reactor Coolants......Page 646
16.5 The Importance of Fluid Friction......Page 647
16.7 The Importance of Bernoulli’s Equation to Nuclear Science and Engineering......Page 648
16.8 Applications of Bernoulli’s Equation to Pipes and Other Simple Structures......Page 649
16.9 Applying Bernoulli’s Equation to a Flow Blockage......Page 652
16.10 The Effect of Directional Changes in the Flow Field on the Coolant Pressure......Page 653
16.11 The Effect of Elevation on the Coolant Pressure......Page 656
16.12 The Effects of Wall Friction on the Local Pressure......Page 657
16.13 The Equivalent Hydraulic Diameter and Its Applications......Page 658
16.14 Calculating the Total Pressure Drop in a Coolant Channel......Page 661
16.15 Understanding Flow and Pressure Changes......Page 663
16.16 Finding the Flow Rates and the Pressures in Nozzles and Diffusers......Page 664
16.17.3 The Hydrostatic Pressure......Page 666
16.18 The Time-Dependent Bernoulli Equation......Page 668
16.19 Estimating the Start- Up Time of a Reactor Coolant Pump from Bernoulli’s Equation......Page 669
16.20 Solving Bernoulli’s Equation with Loss Coefficients and Friction Factors in a Viscous Flow Loop......Page 672
16.22.3 Streamline Flows......Page 673
16.24 Poiseuille’s Equation......Page 674
16.25 Throttling Valves......Page 676
Questions for the Student......Page 678
Exercises for the Student......Page 679
17.2 Viscosity and Fluid Friction......Page 683
17.4 Characteristics of Laminar Flows......Page 685
17.5 Characteristics of Turbulent Flows......Page 686
17.7 Fluid Flow in Pipes, Reactor Coolant Channels, and Tubes......Page 687
17.8 An Introduction to the Reynolds Number......Page 688
17.10 The Reynolds Number for Open Surfaces and Closed Surfaces......Page 689
17.11 The Critical Reynolds Number......Page 690
17.12 Turbulent Flow in Pipes, Reactor Coolant Channels, and Tubes......Page 691
17.13 Reynolds Numbers for Reactor Fuel Assemblies......Page 692
17.15 The Entrance Length and Entrance Effects......Page 693
17.16 Coolant Velocity Profiles for Laminar and Turbulent Flows......Page 695
17.17 Estimating the Wall Shear Stress......Page 697
17.19 Deriving the Darcy Equation for Laminar Flow......Page 698
17.20 Deriving the Darcy Equation for Turbulent Flow......Page 701
17.21 Boundary-Layer Thicknesses......Page 702
17.23 Applying the Darcy Equation to Coolant Channels with Different Cross-Sectional Areas......Page 703
17.24 Turbulent Friction Factors......Page 705
17.25 The Blasius, McAdams, and Petukhov Correlations for Turbulent Flow......Page 706
17.26 Some Observations about the Moody Charts......Page 707
17.28 Correction Factors for Developing Flows......Page 708
17.29 Finding the Hydraulic Diameter of a Reactor Coolant Channel......Page 709
17.30 The Relationship of the Reynolds Number to the Flow Channel Diameter......Page 710
17.31 Finding the Reynolds Number for a PWR Coolant Channel......Page 712
17.32 Finding the Reynolds Number for an LMFBR Coolant Channel......Page 713
17.33 Finding the Reynolds Number for the Pressure Tubes in a PWR Steam Generator......Page 714
17.34 Corrections to the Laminar Friction Factors for a Reactor Fuel Assembly......Page 715
17.35 Friction Factors for a Turbulent Reactor Fuel Assembly......Page 716
17.36 The Rehme Correction for the Turbulent Friction Factor......Page 717
17.38 Comparing the Friction Factors for a Square Fuel Assembly and a Circular Pipe......Page 718
17.40 Finding the Pressure Drop in the Primary Side of a PWR Steam Generator......Page 719
17.41 Bundle-Averaged Friction Factors......Page 720
Questions for the Student......Page 721
Exercises for the Student......Page 723
18.2 Correction Factors for Isothermal and Non- Isothermal Flows......Page 725
18.3 The Temperature Dependence of  the Friction Factor......Page 726
18.4 Effect of Surface Roughness on the Friction Factor......Page 727
18.5 The Pressure Drop when the Flow Is Both Laminar and Turbulent......Page 730
18.6 The Effect of Extended Surfaces, Ribs, and Vanes on the Friction Factor......Page 731
18.7 Loss Coefficients......Page 733
18.8 Pipes and Plenums......Page 736
18.9 The Effect of Grid Spacers on the Pressure Drop......Page 737
18.10 Grid Spacer Loss Coefficients......Page 738
18.12 Loss Coefficients and the Reynolds Number......Page 740
18.13 Orifice Plates......Page 742
18.15 Changing the Core Flow with an Orifice Plate......Page 743
18.16 Core Flow and Pressure Management......Page 744
18.18 Three-Dimensional Effects......Page 746
18.20 Subchannel Cross-Flow......Page 747
18.21 Intra-Assembly Cross-Flow......Page 748
18.22 Core Flow Patterns......Page 749
18.23 The Effects of a Flow Blockage......Page 752
18.24 Estimating the Total Core Pressure Drop......Page 753
18.25 Comparing the Sizes of the Pressure Drops......Page 754
18.26 Loss Coefficients in the Reactor Piping System......Page 756
18.27 Effect of Surface Roughness on the Drag Coefficient......Page 757
18.28 Frictional Forces on Nuclear Fuel Rods and Other Support Structures......Page 759
18.29 Frictional Drag versus Pressure Drag......Page 762
18.30 The Drag Force on a Nuclear Fuel Rod......Page 763
18.32 Noise and Vibration......Page 765
Questions for the Student......Page 766
Exercises for the Student......Page 768
19.1 Reactor Coolants and Their Properties......Page 771
19.4 Factors in Selecting a Reactor Coolant......Page 772
19.4.2 Physical Factors......Page 773
19.5 Reactor Coolants Used in Different Reactor Types......Page 774
19.5.3 Fast Reactor Coolants......Page 775
19.6 Physical Properties of Reactor Coolants......Page 776
19.7 Reactor Coolants and Representative Flow Rates......Page 777
19.8 Work Performed by a RCP (Pump Work)......Page 779
19.9 Flow Work......Page 780
19.11 Calculating the Pumping Power for a Complete Loop......Page 782
19.12 Corrections to the Pumping Power for Pump Efficiency......Page 783
19.14 Finding the Pumping Power for the Primary Side of a PWR Steam Generator......Page 784
19.16 Coolant Pump Reliability......Page 786
19.18 Pump Start- Up Times......Page 787
19.19 Estimating the Start- Up Time for a RCP from Bernoulli’s Equation......Page 788
19.20 Solving the Momentum Equations with Loss Coefficients and Friction in a Viscous Coolant Loop......Page 792
19.21 Pump Performance Parameters......Page 793
19.

✦ Subjects

Nuclear reactors--Cooling;Nuclear reactors--Fluid dynamics;Nuclear reactors--Thermodynamics;Thermal hydraulics;Nuclear reactors -- Cooling;Nuclear reactors -- Thermodynamics;Nuclear reactors -- Fluid dynamics