Hinweis: Dieser Artikel kann nur an eine deutsche Lieferadresse ausgeliefert werden.
JOHN C. LEE, PHD, is professor in the Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor.
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
