| 청구기호 |
TK9165 .L44 2020 |
| 형태사항 |
1 online resource (xxiii, 631 pages)
|
| 언어 |
English |
| 서지주기 |
Includes bibliographical references and index.
|
| 내용 |
Cover -- Title Page -- Copyright -- Contents -- Preface -- Permissions and Copyrights -- List of Tables -- List of Figures -- Chapter 1 Nuclear Power Plants -- 1.1 History and Current Status of Nuclear Power Plants -- 1.2 Basic Features of Nuclear Power Plants -- 1.3 Pressurized Water Reactor Systems -- 1.4 Boiling Water Reactor Systems -- 1.5 Advanced Reactor Designs -- References -- Problems -- Chapter 2 Neutron-nucleus Reaction and Neutron Cross Section -- 2.1 Neutron-nucleus Reaction Probability and Neutron Cross Section -- 2.2 Mechanisms of Neutron-nucleus Interaction
2.3 Nuclear Fission Process -- 2.4 Two-body Collision Mechanics and Center-of-mass System -- 2.5 Single-Level Breit-Wigner Formula for Resonance Reaction -- 2.6 Differential Scattering Cross Section and Scattering Kernel -- 2.6.1 Differential Microscopic Scattering Cross Section -- 2.6.2 Scattering Kernel for Isotropic Scattering in CM Frame -- 2.7 Further Remarks on Neutron Cross Section -- References -- Problems -- Chapter 3 Neutron Flux -- 3.1 Neutron Flux and Current -- 3.2 Rate of Neutron-Nucleus Interaction -- 3.3 Neutron Energy Distribution and Effective Thermal Cross Section
3.4 Application to a -Absorber -- References -- Problems -- Chapter 4 Derivation of the Neutron Diffusion Equation -- 4.1 Basic Assumptions for Neutron Balance Statement -- 4.2 Neutron Balance Equation -- 4.3 Neutron Source Term -- 4.4 Fick's Law of Neutron Current -- 4.5 Neutron Transport Equation and p1 Approximation -- 4.6 Remarks on Diffusion Coefficient -- 4.7 Limitations of Neutron Diffusion Theory -- 4.8 One-Group Neutron Diffusion Equation -- 4.9 Summary Discussion of Diffusion Equation -- References -- Problems -- Chapter 5 Applications of the One-Group Neutron Diffusion Equation
5.1 Boundary Conditions for Diffusion Equation -- 5.2 Solution of Steady-State Diffusion Equation -- 5.2.1 Flux in Non-multiplying Media with Localized Sources -- 5.2.2 Flux in Non-multiplying Media with Distributed Sources -- 5.3 Neutron Flux in Multiplying Medium and Criticality Condition -- 5.3.1 Criticality and Buckling -- 5.3.2 Effective Multiplication Factor -- 5.3.3 Eigenfunctions of Diffusion Equation and Buckling -- 5.4 Four- and Six-Factor Formulas for Multiplication Factor -- 5.5 Concluding Remarks -- References -- Problems
Chapter 6 Numerical Solution of the Neutron Diffusion Equation -- 6.1 Finite Difference Form of Diffusion Equation -- 6.2 Flux Solution Algorithm: Inner Iteration -- 6.3 Boundary Conditions for Difference Equation -- 6.4 Source or Outer Iteration -- 6.5 Relative Power Distribution and Overall Flow Chart -- 6.6 Single-Channel Flux Synthesis -- 6.7 Multidimensional Finite Difference Formulation -- 6.7.1 Two-Dimensional Matrix Formulation -- 6.7.2 Three-Dimensional Formulation -- 6.7.3 Convergence Properties of Matrix Iteration Schemes -- 6.8 Coarse-Mesh Diffusion Equation Solver
|
| 주제 |
Nuclear engineering --Textbooks.
Nuclear reactors --Textbooks.
Nuclear engineering. --fast --(OCoLC)fst01040032
Nuclear reactors. --fast --(OCoLC)fst01040734
|
| 보유판 및 특별호 저록 |
Print version: Lee, John C., 1941- Nuclear reactor physics and engineering. Hobken, NJ, USA : John Wiley & Sons, Inc., 2019 9781119582328 , 2019030441
|
| LCCN |
2019030442
|
| ISBN |
9781119582359, 1119582350, 9781119582281, 1119582288, 9781119582342, 1119582342, 9781119582328, 1119582326
|
| QR CODE |
|
