Nuclear reactor physics and engineering

著者

書誌事項

Nuclear reactor physics and engineering

John C. Lee

Wiley, 2020

電子リソースにアクセスする 全1件

大学図書館所蔵 件 / 全2件

この図書・雑誌をさがす

注記

Includes bibliographical references and index

内容説明・目次

内容説明

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 fluid 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.

目次

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

「Nielsen BookData」 より

詳細情報

ページトップへ