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Nuclear reactor physics and engineering /
"The book has been developed to introduce undergraduate and graduate students in nuclear engineering, as well as practicing engineers, to basic concepts of nuclear reactor physics and applications of the concepts to the analysis, design, control, and operation of nuclear reactors. The basic con...
| Clasificación: | Libro Electrónico |
|---|---|
| Autor principal: | |
| Formato: | Electrónico eBook |
| Idioma: | Inglés |
| Publicado: |
Hobken, NJ :
John Wiley & Sons,
2020.
|
| Temas: | |
| Acceso en línea: | Texto completo |
MARC
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| 100 | 1 | |a Lee, John C., |d 1941- |e author. | |
| 245 | 1 | 0 | |a Nuclear reactor physics and engineering / |c John C. Lee, University of Michigan, Ann Arbor, Michigan. |
| 264 | 1 | |a Hobken, NJ : |b John Wiley & Sons, |c 2020. | |
| 264 | 4 | |c Ã2020 | |
| 300 | |a 1 online resource (xxiii, 631 pages) | ||
| 336 | |a text |b txt |2 rdacontent | ||
| 337 | |a computer |b n |2 rdamedia | ||
| 338 | |a online resource |b nc |2 rdacarrier | ||
| 504 | |a Includes bibliographical references and index. | ||
| 520 | |a "The book has been developed to introduce undergraduate and graduate students in nuclear engineering, as well as practicing engineers, to basic concepts of nuclear reactor physics and applications of the concepts to the analysis, design, control, and operation of nuclear reactors. The basic concepts are discussed and the associated mathematical formulations presented with the understanding that the reader has solid background in differential equations and linear algebra. A focus has been placed on the use of neutron diffusion theory, with a minimum use of the neutron transport equation, for the development of techniques for lattice physics and global reactor system studies. When the neutron transport equation is used, effort is made to stay with onedimensional forms of the Boltzmann equation and Legendre polynomials, without invoking the fullblown threedimensional Boltzmann equation and spherical harmonics. Recent developments in numerical algorithms, including the Krylov subspace method, for efficient solution of large matrix equations have been discussed as part of the numerical solution algorithms for the neutron diffusion equation"-- |c Provided by publisher. | ||
| 588 | 0 | |a Online resource; title from digital title page (viewed on April 21, 2020). | |
| 505 | 0 | |a 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 | |
| 505 | 8 | |a 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 | |
| 505 | 8 | |a 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 | |
| 505 | 8 | |a 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 | |
| 505 | 8 | |a 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 | |
| 590 | |a Knovel |b ACADEMIC - Electrical & Power Engineering | ||
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| 650 | 0 | |a Nuclear reactors |v Textbooks. | |
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| 650 | 7 | |a Nuclear reactors |2 fast | |
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| 655 | 7 | |a Textbooks. |2 lcgft | |
| 776 | 0 | 8 | |i Print version: |a Lee, John C., 1941- |t Nuclear reactor physics and engineering. |d Hobken, NJ, USA : John Wiley & Sons, Inc., 2019 |z 9781119582328 |w (DLC) 2019030441 |
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