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

JOHN C. LEE, PHD, is professor in the Department of Nuclear Engineering and Radiological Sciences, University of Michigan, Ann Arbor.