‏757.00 ₪

Nuclear Reactor Physics and Engineering

‏757.00 ₪

ISBN13

9781119582328

יצא לאור ב

Hoboken

זמן אספקה

21 ימי עסקים

עמודים

624

פורמט

Hardback

תאריך יציאה לאור

28 בפבר׳ 2020

לדלג לסוף של גלריית תמונות

לדלג להתחלה של גלריית תמונות

פרטים

An introductory text for broad areas of nuclear reactor physics Nuclear Reactor Physics and Engineering offers information on analysis, design, control, and operation of nuclear reactors. The author-a noted expert on the topic-explores the fundamentals and presents the mathematical formulations that are grounded in differential equations and linear algebra. The book puts the focus on the use of neutron diffusion theory for the development of techniques for lattice physics and global reactor system analysis. The author also includes recent developments in numerical algorithms, including the Krylov subspace method, and the MATLAB software, including the Simulink toolbox, for efficient studies of steady-state and transient reactor configurations. In addition, nuclear fuel cycle and associated economics analysis are presented, together with the application of modern control theory to reactor operation. This important book: Provides a comprehensive introduction to the fundamental concepts of nuclear reactor physics and engineering Contains information on nuclear reactor kinetics and reactor design analysis Presents illustrative examples to enhance understanding Offers self-contained derivation of ?uid conservation equations Written for undergraduate and graduate students in nuclear engineering and practicing engineers, Nuclear Reactor Physics and Engineering covers the fundamental concepts and tools of nuclear reactor physics and analysis.

מידע נוסף

מידע נוסף
עמודים	624
פורמט	Hardback
ISBN10	1119582326
יצא לאור ב	Hoboken
תאריך יציאה לאור	28 בפבר׳ 2020
תוכן עניינים	Preface ix Permissions and Copyrights xi 1 Nuclear Power Plants 1 1.1 History and Current Status of Nuclear Power Plants 1 1.2 Basic Features of Nuclear Power Plants 3 1.3 Pressurized Water Reactor System 4 1.4 Boiling Water Reactor System 9 1.5 Advanced Reactor Designs 14 References 20 Problems 22 2 Neutron-nucleus Reactions and Neutron Cross Section 23 2.1 Neutron-nucleus Reaction Probability and Neutron Cross Section 24 2.2 Mechanisms of Neutron-nucleus Interactions 25 2.3 Nuclear Fission Process 27 2.4 Two-body Collision Mechanics and Center-of-mass System 31 2.5 Single-Level Breit-Wigner Formula for Resonance Reaction 36 2.6 Differential Scattering Cross Section and Scattering Kernel 39 2.6.1 Differential Microscopic Scattering Cross Section 39 2.6.2 Scattering Kernel for Isotropic Scattering in CM Frame 40 2.7 Further Remarks on Neutron Cross Section 42 References 45 Problems 48 3 Neutron Flux, Reaction Rate, and Effective Cross Section 51 3.1 Neutron Flux and Current 52 3.2 Rate of Neutron-nucleus Interactions 57 3.3 Neutron Energy Distribution and Effective Thermal Cross Section 59 3.4 Application to a 1/v-Absorber 63 References 64 Problems 64 4 Derivation of the Neutron Diffusion Equation 67 4.1 Basic Assumptions for Neutron Balance Statement 68 4.2 Neutron Balance Equation 69 4.3 Neutron Source Term 72 4.4 Fick's Law of Neutron Current 73 4.5 Neutron Transport Equation and P1 Approximation 76 4.6 Remarks on the Diffusion Coefficient 80 4.7 Limitations of Neutron Diffusion Theory 81 4.8 One-Group Neutron Diffusion Equation 82 4.9 Summary Discussion on the Diffusion Equation 83 References 83 Problems 84 5 Applications of One-Group Neutron Diffusion Equation 85 5.1 Boundary Conditions for Diffusion Equation 86 5.2 Solution of the Steady-state Diffusion Equation 89 5.2.1 Flux in Non-multiplying Media with Localized Sources 89 5.2.2 Flux in Non-multiplying Media with Distributed Sources 96 5.3 Neutron Flux in Multiplying Medium and Criticality Condition 99 5.3.1 Criticality and Buckling 99 5.3.2 Effective Multiplication Factor 100 5.3.3 Eigenfunctions of Diffusion Equation and Buckling 102 5.4 Four-and Six-factor Formulas for Multiplication Factor 106 5.5 Concluding Remarks 108 References 108 Problems 108 6 Numerical Solution of Neutron Diffusion Equation 113 6.1 Finite Difference Form of Diffusion Equation 114 6.2 Flux Solution Algorithm: Inner Iteration 117 6.3 Boundary Conditions for Difference Equation 119 6.4 Source or Outer Iteration 121 6.5 Relative Power Distribution and Overall Flow Chart 123 6.6 Single Channel Flux Synthesis 126 6.7 Multi-dimensional Finite Difference Formulation 128 6.7.1 Two-dimensional Matrix Formulation 128 6.7.2 Three-dimensional Formulation 132 6.7.3 Convergence Properties of Matrix Iteration Schemes 133 6.8 Coarse-mesh Diffusion Equation Solver 134 6.8.1 Nodal Expansion Method 134 6.8.2 Pin Power Reconstruction Algorithm 136 6.9 Krylov Subspace Method as Diffusion Equation Solver 137 References 140 Problems 141 7 Applications of Two-Group Neutron Diffusion Equation 143 7.1 Derivation of Multi-group Neutron Diffusion Equation 144 7.2 Steady-state Multi-group Diffusion Equation 147 7.3 Two-group Form of Effective Multiplication Factor 149 7.4 General Two-group Diffusion Analysis 152 References 154 Problems 154 8 Nuclear Reactor Kinetics 157 8.1 Derivation of Point Kinetics Equation 158 8.1.1 Representation of Delayed Neutron Production 158 8.1.2 Point Kinetics Approximation 159 8.1.3 One-group Delayed Neutron Model 161 8.2 Solution of Point Kinetics Equation without Feedback 162 8.2.1 Step Insertion of Reactivity 162 8.2.2 Prompt Jump or Zero Lifetime Approximation 165 8.2.3 Inhour Equation 166 8.2.4 Linearized Kinetics Equation and Transfer Function 168 8.2.5 Infinite Delayed Approximation 171 8.3 State Space Representation of Point Kinetics Equation 171 8.4 Point Kinetics Equation with Feedback 174 8.4.1 The Ergen-Weinberg Model 174 8.4.2 The Nordheim-Fuchs Model 177 8.5 Reactivity Measurements 178 8.6 System Stability Analysis 181 8.7 Reactor Noise Analysis and Correlation Functions 184 8.7.1 Reactor Noise Analysis 185 8.7.2 Correlation Function Techniques 188 8.8 Point Reactor and Space-dependent Reactor Kinetics 190 References 191 Problems 191 9 Fast Neutron Spectrum Calculation 195 9.1 Neutron Balance Equation and Slowing Down Density 196 9.2 Elastic Scattering and Lethargy Variable 200 9.3 Neutron Slowing Down in Infinite Medium 201 9.3.1 Slowing Down in First Collision Interval 202 9.3.2 Slowing Down below First Collision Interval 206 9.4 Resonance Escape Probability 209 9.4.1 Effective Resonance Integral 209 9.4.2 Energy Self-shielding Factor 211 9.4.3 Wide Resonance Approximation 212 9.4.4 Probability Table or Subgroup Method 213 9.5 Doppler Broadening of Resonances 215 9.5.1 Qualitative Description of Doppler Broadening 215 9.5.2 Analytical Treatment of Doppler Broadening 217 9.6 Fermi Age Theory 220 9.7 Comments on Lattice Physics Analysis 223 References 224 Problems 224 10 Perturbation Theory and Adjoint Flux 227 10.1 Operator Notation for Neutron Diffusion Equation 228 10.2 Adjoint Operator and Adjoint Flux 228 10.3 First-order Perturbation Theory 230 10.4 Adjoint Flux for Control Rod Worth Calculation 232 10.5 Adjoint Flux for Variational Formulation 234 10.6 Adjoint Flux for Detector Response Calculation 235 10.7 Adjoint Formulation for Flux Perturbation Calculation 236 10.8 Concluding Remarks on Adjoint Flux 240 References 240 Problems 240 11 Lattice Physics Analysis of Heterogeneous Cores 243 11.1 Material Heterogeneity and Flux Distribution in Unit Cell 245 11.2 Neutronic Advantages of Fuel Lumping 246 11.3 Diffusion Theory Model for Thermal Utilization 250 11.4 Improved Method for Thermal Disadvantage Factor 254 11.4.1 Blackness or Simplified Collision Probability Method 254 11.4.2 Amouyal-Benoist-Horowitz Method 255 11.5 Resonance Escape Probability for Heterogeneous Cell 257 11.5.1 Spatial Self-shielding Factor for Heterogeneous Unit Cell 258 11.5.2 Engineering Approaches for Resonance Integral Calculation 262 11.5.3 Implementation in the CPM-3 Code 264 11.6 Thermal Spectrum Calculation 265 11.6.1 Wigner-Wilkins Model 266 11.6.2 Qualitative Behavior of Thermal Neutron Spectrum 267 11.7 Integral Transport Methods 268 11.8 B1 Formulation for Spectrum Calculation 271 11.8.1 Basic Structure of B1 Formulation 271 11.8.2 Numerical Solution of B1 Equations 274 11.9 Lattice Physics Methodology for Fast Reactor 276 11.9.1 Bondarenko Formulation for Self-Shielding Factor 276 11.9.2 MC2-3 Code 278 11.9.3 ERANOS System 278 11.10 Monte Carlo Lattice Physics Analysis 278 11.11 Overall Reactor Physics Analysis 279 References 279 Problems 282 12 Nuclear Fuel Cycle Analysis and Management 285 12.1 Nuclear Fuel Management 286 12.2 Key Nuclide Chains for Nuclear Fuel Cycle 289 12.3 Fuel Depletion Model 290 12.3.1 Fuel Depletion Equation 291 12.3.2 Solution of Pointwise Depletion Equation 292 12.3.3 Fuel Depletion Equation in Global MGD Calculation 293 12.3.4 Simple Model for Fuel Burnup Estimation 296 12.4 Equilibrium Cycle and Mass Balance 297 12.4.1 Nuclide Balance Statement 297 12.4.2 Material Flow Sheet 298 12.4.3 REBUS Equilibrium Inventory Calculation 300 12.5 Simplified Cycling Model 301 12.5.1 Reactivity-based Instant Cycling Method 302 12.5.2 Application of Instant Cycling Method 303 12.6 Xenon Fission Product Buildup 307 12.6.1 Mechanism for 135Xe Production and Balance Equation 307 12.6.2 Time-domain Solution of Xe-I Balance Equation 308 12.6.3 Effect of Samarium Buildup 311 12.7 General Incore Management Considerations 312 12.7.1 Reactivity Variation over Fuel Cycle 312 12.7.2 Thermal-hydraulic Feedback and Power Distribution 313 12.7.3 Control Requirements for Light Water Reactor 313 12.7.4 Power Distribution Control 315 12.8 Radioactive Waste and Used Nuclear Fuel Management 317 12.8.1 Classification of Radioactive Waste 317 12.8.2 Characteristics of Radioactive Waste 317 12.8.3 Status of Used Nuclear Fuel Inventory 319 12.8.4 Partition and Transmutation of Waste 320 References 323 Problems 325 13 Thermal-Hydraulic Analysis of Reactor Systems 327 13.1 Empirical Laws for Energy and Momentum Transport 328 13.1.1 Fourier's Law of Heat Conduction 329 13.1.2 Newton's Law of Viscosity 329 13.1.3 Newton's Law of Cooling 330 13.2 Derivation of Fluid Conservation Equations 331 13.2.1 Equation of Continuity 331 13.2.2 Equation of Motion and Navier-Stokes Equation 332 13.2.3 Equations of Energy Conservation 334 13.2.4 Comments on the Fluid Conservation Equations 337 13.3 Simple Solutions of Fluid Conservation Equations 337 13.3.1 Heat Conduction in Cylindrical Fuel Rod 344 13.3.2 Heat Conduction through Composite Wall 346 13.3.3 Forced Convection in Laminar Flow 348 13.3.4 Velocity Distribution in Turbulent Flow 351 13.3.5 Friction Factor and Hydraulic Diameter 352 13.4 Conservation Equations for Channel Flow 353 13.4.1 Equation of Continuity 353 13.4.2 Equation of Motion and Pressure Drop 354 13.4.3 Equation of Energy Conservation 355 13.5 Axial Temperature Distribution in Reactor Core 356 13.5.1 Power Distribution and Heat Flux in Reactor Core 356 13.5.2 Axial Temperature Profile in PWR Core 357 13.5.3 Axial Temperature Profile in BWR Core 360 13.5.4 Hot Channel Factors 361 13.6 Boiling Heat Transfer and Two-Phase Flow 364 13.6.1 Pool Boiling Regimes 364 13.6.2 Flow Boiling Regimes and Two-Phase Flow Patterns 365 13.6.3 Homogeneous Equilibrium Flow Model 367 13.6.4 Slip Flow Model 368 13.6.5 Drift Flux Model 374 13.7 Thermal Hydraulic Limitations and Power Capability 376 13.7.1 DNB Ratio and Number of Fuel Rods Reaching DNB 376 13.7.2 Non-uniform Heat Flux Correction 378 13.7.3 Iterative Determination of DNB Ratio 380 13.7.4 Power Capability Determination 381 13.8 Thermal-Hydraulic Models for Nuclear Plant Analysis 382 13.8.1 Light Water Reactor System Modeling Codes 384 13.8.2 Subchannel Analysis Codes 387 13.8.3 Sodium-cooled Fast Reactor Codes 387 13.8.4 Containment Analysis Codes 389 13.8.5 Computational Fluid Dynamics Codes 390 13.9 Comments on Thermal-Hydraulic Models 391 References 391 Problems 393 14 Power Coefficients of Reactivity 397 14.1 Physical Phenomena Affecting Core Reactivity 398 14.2 Relationship between Reactivity Coefficients 399 14.3 Two-group Representation of Reactivity Feedback 401 14.4 Parametric Dependence of LWR Reactivity Coefficients 402 14.5 Reactivity Coefficients in Sodium-Cooled Fast Reactor 404 14.6 Quasi-static Reactivity Feedback Model for Sodium-Cooled Fast Reactor 405 References 408 Problems 408 15 Nuclear Energy Economics 411 15.1 Electrical Energy Cost 412 15.2 Overview on Engineering Economics 414 15.3 Calculation of Nuclear Electricity Generation Cost 415 15.3.1 Capital Cost 415 15.3.2 Fuel Cost 416 15.3.3 Operation and Maintenance Cost 420 15.3.4 Decommissioning Cost 421 15.4 Impact of Increased Capital and O&M Costs 422 References 423 Problems 424 16 Space-Time Kinetics and Reactor Control 425 16.1 Space-time Reactor Kinetics 426 16.1.1 Numerical Solution of Space-time Kinetics Equation 426 16.1.2 Direct Solution of Space-time Kinetics Equation 427 16.1.3 Quasi-static Formulation of Kinetics Equation 428 16.1.4 Reactivity Determination from Multiple Detectors 430 16.2 Space-time Power Oscillations due to Xenon Poisoning 433 16.2.1 Modal Analysis of Space-time Xenon-power Oscillations 434 16.2.2 Stability of Space-time Xenon-power Oscillations 438 16.2.3 Space-time Xenon-power Oscillations in X-Y plane 442 16.3 Time-optimal Reactor Control 445 16.3.1 Optimal Control of Xenon-induced Transients 445 16.3.2 Control of Spatial Xenon Oscillations 448 16.4 Model Based Reactor Control 452 16.4.1 Linear Quadratic Regulator 452 16.4.2 H2 Controller 454 16.4.3 H Controller 456 16.4.4 Augmented Plant Representation 457 16.5 Alternate Reactor Control Techniques 459 16.6 Kalman Filtering for Optimal System Estimation 463 References 466 Problems 468 17 Elements of Neutron Transport Theory 471 17.1 Collision Probability Method 471 17.1.1 Integral Transport Equation 472 17.1.2 Reciprocity Relationship 474 17.1.3 Transport Kernel and Collision Probability 474 17.2 First-Flight Escape Probability and Dirac Chord Method 476 17.3 Flux Depression Calculation and Blackness 480 17.3.1 Escape Probability and Flux Depression Factor 481 17.3.2 Net Escape Probability and Collision Probability 482 17.3.3 Dancoff Factor for Fuel Lattice 483 17.4 Numerical Solution of Neutron Transport Equation 485 17.4.1 Collision Probability Calculation for Annular Geometry 485 17.4.2 Discrete Ordinates Method 489 17.4.3 Method of Characteristics 491 17.4.4 Monte Carlo Algorithm 492 References 494 Problems 495 Appendix A: Key Physical Constants 497 Appendix B: Comparison of Major Reactor Types 499 References 500 Appendix C: Special Mathematical Functions 503 C.1 Gamma Function 503 C.2 Legendre Polynomial and Spherical Harmonics 505 C.3 Bessel Function 507 C.4 Dirac Delta Function 510 References 510 Appendix D: Integral Transforms 511 D.1 Laplace Transform 511 D.2 Fourier Transform 512 D.3 Jordan's Lemma 512 References 514 Appendix E: Calculus of Variation for Optimal Control Formulation 515 E.1 Euler-Lagrange and Hamilton Equations 515 E.2 Pontryagin's Maximum Principle 517 References 521 Appendix F: Kalman Filter Algorithm 523 F.1 Linear Kalman Filter 523 F.2 Unscented Kalman Filter 527 References 528 Answers to Selected Problems 529 Index 541
זמן אספקה	21 ימי עסקים