Nuclear Reactor Physics

The third, revised edition of this popular textbook and reference, which has been translated into Russian and Chinese, expands the comprehensive and balanced coverage of nuclear reactor physics to include recent advances in understanding of this topic. The first part of the book covers basic reactor physics, including, but not limited to nuclear reaction data, neutron diffusion theory, reactor criticality and dynamics, neutron energy distribution, fuel burnup, reactor types and reactor safety. The second part then deals with such physically and mathematically more advanced topics as neutron transport theory, neutron slowing down, resonance absorption, neutron thermalization, perturbation and variational methods, homogenization, nodal and synthesis methods, and space-time neutron dynamics. For ease of reference, the detailed appendices contain nuclear data, useful mathematical formulas, an overview of special functions as well as introductions to matrix algebra and Laplace transforms. With its focus on conveying the in-depth knowledge needed by advanced student and professional nuclear engineers, this text is ideal for use in numerous courses and for self-study by professionals in basic nuclear reactor physics, advanced nuclear reactor physics, neutron transport theory, nuclear reactor dynamics and stability, nuclear reactor fuel cycle physics and other important topics in the field of nuclear reactor physics.

Autorentext
Weston M. Stacey is Professor of Nuclear Engineering at the Georgia Institute of Technology. His career spans more than 50 years of research and teaching in nuclear reactor physics, fusion plasma physics and fusion and fission reactor conceptual design. He led the IAEA INTOR Workshop (1979-88) that led to the present ITER project, for which he was awarded the US Department of Energy Distinguished Associate Award and the Department of Energy Certificates of Appreciation. Professor Stacey is a Fellow of the American Nuclear Society and of the American Physical Society. He is the recipient of several prizes, among them the American Nuclear Society Seaborg Medal for Nuclear Research and the Wigner Reactor Physicsist Award, and the author of ten previous books and numerous research papers.

Inhalt
Preface xxiii Preface to Second Edition xxvii Preface to Third Edition xxix Part 1 Basic Reactor Physics 1 1 NeutronNuclear Reactions 3 1.1 Neutron-Induced Nuclear Fission 3 1.2 Neutron Capture 12 1.3 Neutron Elastic Scattering 19 1.4 Summary of Cross Section Data 23 1.5 Evaluated Nuclear Data Files 25 1.6 Elastic Scattering Kinematics 25 2 Neutron Chain Fission Reactors 33 2.1 Neutron Chain Fission Reactions 33 2.2 Criticality 37 2.3 Time Dependence of a Neutron Fission Chain Assembly 38 2.4 Classification of Nuclear Reactors 40 3 Neutron Diffusion and Transport Theory 43 3.1 Derivation of One-Speed Diffusion Theory 43 3.2 Solutions of the Neutron Diffusion Equation in Nonmultiplying 3.3 Diffusion Kernels and Distributed Sources in a Homogeneous 3.4 Albedo Boundary Condition 52 3.5 Neutron Diffusion and Migration Lengths 53 3.6 Bare Homogeneous Reactor 57 3.7 Reflected Reactor 62 3.8 Homogenization of a Heterogeneous FuelModerator 3.9 Control Rods 72 3.10 Numerical Solution of Diffusion Equation 76 3.11 Nodal Approximation 82 3.12 Transport Methods 84 4 Neutron Energy Distribution 101 4.1 Analytical Solutions in an Infinite Medium 101 4.2 Multigroup Calculation of Neutron Energy Distribution in an Infinite 4.3 Resonance Absorption 118 4.4 Multigroup Diffusion Theory 127 5 Nuclear Reactor Dynamics 141 5.1 Delayed Fission Neutrons 141 5.2 Point Kinetics Equations 145 5.3 PeriodReactivity Relations 146 5.4 Approximate Solutions of the Point Neutron Kinetics Equations 148 5.5 Delayed Neutron Kernel and Zero-Power Transfer Function 153 5.6 Experimental Determination of Neutron Kinetics Parameters 155 5.7 Reactivity Feedback 160 5.8 Perturbation Theory Evaluation of Reactivity Temperature 5.9 Reactor Stability 171 5.10 Measurement of Reactor Transfer Functions 179 5.11 Reactor Transients with Feedback 184 5.12 Reactor Fast Excursions 187 5.13 Numerical Methods 192 6 Fuel Burnup 197 6.1 Changes in Fuel Composition 197 6.2 Samarium and Xenon 211 6.3 Fertile-to-Fissile Conversion and Breeding 217 6.4 Simple Model of Fuel Depletion 219 6.5 Fuel Reprocessing and Recycling 221 6.6 Radioactive Waste 225 6.7 Burning Surplus Weapons-Grade Uranium and Plutonium 232 6.8 Utilization of Uranium Energy Content 234 6.9 Transmutation of Spent Nuclear Fuel 236 6.10 Closing the Nuclear Fuel Cycle 242 7 Nuclear Power Reactors 247 7.1 Pressurized Water Reactors 247 7.2 Boiling Water Reactors 249 7.3 Pressure Tube Heavy WaterModerated Reactors 253 7.4 Pressure Tube Graphite-Moderated Reactors 255 7.5 Graphite-Moderated Gas-Cooled Reactors 258 7.6 Liquid Metal Fast Reactors 260 7.7 Other Power Reactors 265 7.8 Characteristics of Power Reactors 266 7.9 Advanced Generation-III Reactors 267 7.10 Advanced Generation-IV Reactors 271 7.11 Advanced Subcritical Reactors 274 7.12 Nuclear Reactor Analysis 276 7.13 Interaction of Reactor Physics and Reactor Thermal Hydraulics 281 8 Reactor Safety 285 8.1 Elements of Reactor Safety 285 8.2 Reactor Safety Analysis 287 8.3 Quantitative Risk Assessment 289 8.4 Reactor Accidents 294 8.5 Passive Safety 300 Part 2 Advanced Reactor Physics 305 9 Neutron Transport Theory 307 9.1 Neutron Transport Equation 307 9.2 Integral Transport Theory 312 &l...

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