JOHN C. LEE, PHD, is professor in the Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor.
Inhaltsangabe
Preface xiv Permissions and Copyrights xvi List of Tables xviii List of Figures xix 1 Nuclear Power Plants 1 2 Neutronnucleus Reaction and Neutron Cross Section 27 3 Neutron Flux, Reaction Rate, and Effective Cross Section 59 4 Derivation of the Neutron Diffusion Equation 77 5 Applications of the One-Group Neutron Diffusion Equation 99 6 Numerical Solution of the Neutron Diffusion Equation 131 7 Applications of the Two-Group Neutron Diffusion Equation 165 8 Nuclear Reactor Kinetics 181 9 Fast Neutron Spectrum Calculation 219 10 Perturbation Theory and Adjoint Flux 255 11 Lattice Physics Analysis of Heterogeneous Cores 273 12 Nuclear Fuel Cycle Analysis and Management 323 13 Thermal-Hydraulic Analysis of Reactor Systems 373 14 Power Coefficients of Reactivity 455 15 Nuclear Energy Economics 471 16 Space-Time Kinetics and Reactor Control 489 17 Elements of Neutron Transport Theory 543 Appendix A: Key Physical Constants 575 Appendix B: Comparison of Major Reactor Types 577 Appendix C: Special Mathematical Functions 581 Appendix D: Integral Transforms 591 Appendix E: Calculus of Variation for Optimal Control Formulation 595 Appendix F: Kalman Filter Algorithm 603 Answers to Selected Problems 609 Index 621
Preface xiv Permissions and Copyrights xvi List of Tables xviii List of Figures xix 1 Nuclear Power Plants 1 2 Neutronnucleus Reaction and Neutron Cross Section 27 3 Neutron Flux, Reaction Rate, and Effective Cross Section 59 4 Derivation of the Neutron Diffusion Equation 77 5 Applications of the One-Group Neutron Diffusion Equation 99 6 Numerical Solution of the Neutron Diffusion Equation 131 7 Applications of the Two-Group Neutron Diffusion Equation 165 8 Nuclear Reactor Kinetics 181 9 Fast Neutron Spectrum Calculation 219 10 Perturbation Theory and Adjoint Flux 255 11 Lattice Physics Analysis of Heterogeneous Cores 273 12 Nuclear Fuel Cycle Analysis and Management 323 13 Thermal-Hydraulic Analysis of Reactor Systems 373 14 Power Coefficients of Reactivity 455 15 Nuclear Energy Economics 471 16 Space-Time Kinetics and Reactor Control 489 17 Elements of Neutron Transport Theory 543 Appendix A: Key Physical Constants 575 Appendix B: Comparison of Major Reactor Types 577 Appendix C: Special Mathematical Functions 581 Appendix D: Integral Transforms 591 Appendix E: Calculus of Variation for Optimal Control Formulation 595 Appendix F: Kalman Filter Algorithm 603 Answers to Selected Problems 609 Index 621
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