Neutronic Analysis For Nuclear Reactor Systems
Springer International Publishing (Verlag)
9783319429625 (ISBN)
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Dr. Bahman Zohuri is founder of Galaxy Advanced Engineering, Inc. a consulting company that he formed upon leaving the semiconductor and defense industries after many years as a Senior Process Engineer for corporations including Westinghouse and Intel, and then as Senior Chief Scientist at Lockheed Missile and Aerospace Corporation. During his time with Westinghouse Electric Corporation, he performed thermal hydraulic analysis and natural circulation for Inherent Shutdown Heat Removal System (ISHRS) in the core of a Liquid Metal Fast Breeder Reactor (LMFBR). While at Lockheed, he was responsible for the study of vulnerability, survivability and component radiation and laser hardening for Defense Support Program (DSP), Boost Surveillance and Tracking Satellites (BSTS) and Space Surveillance and Tracking Satellites (SSTS). He also performed analysis of characteristics of laser beam and nuclear radiation interaction with materials, Transient Radiation Effects in Electronics (TREE), Electromagnetic Pulse (EMP), System Generated Electromagnetic Pulse (SGEMP), Single-Event Upset (SEU), Blast and, Thermo-mechanical, hardness assurance, maintenance, and device technology. His consultancy clients have included Sandia National Laboratories, and he holds patents in areas such as the design of diffusion furnaces, and Laser Activated Radioactive Decay. He is the author of several books on nuclear engineering heat transfer.
'Table of Contents About the Authors Preface Acknowledgment Chapter One: Neutron Physics Background 1.0 Nuclei - Sizes, Composition, and Binding Energies 1.1 Decay of a Nucleus 1.2 Distribution of Nuclides and Nuclear Fission/Nuclear Fusion 1.3 Neutron-Nucleus Interaction 1.3.1 Nuclear Reactions Rates and Neutron Cross Sections 1.3.2 Effects of Temperature on Cross Section 1.3.3 Nuclear Cross Section Processing Codes 1.3.4 Energy Dependence of Neutron Cross Sections 1.3.5 Types of Interactions 1.4 Mean Free Path 1.5 Nuclear Cross Section and Neutron Flux Summary 1.6 Fission 1.7 Fission Spectra 1.8 The Nuclear Fuel 1.6.1 Fertile Material 1.9 Liquid Drop Model of a Nucleus 1.10 Summary of Fission Process 1.11 Reactor Power Calculation 1.12 Relationship between Neutron Flux and Reactor Power 1.13 References 1.14 Problems Chapter Two: Modeling Neutron Transport and Interactions 2.0 Transport Equations 2.1 Reaction Rates 2.2 Reactor Power Calculation 2.3 Relationship between Neutron Flux and Reactor Power 2.4 Neutron Slowing Down and Thermalization 2.5 Macroscopic Slowing Down Power 2.6 Moderate Ratio 2.7 Integro-Differential Equation (Maxwell-Boltzmann Equation) 2.8 Integral Equation 2.9 Multigroup Diffusion Theory 2.10 The Multigroup Equations 2.11 Generating the Coefficients 2.12 Simplifications 2.13 Nuclear Criticality Concepts 2.14 Criticality Calculation 2.15 The Multiplication Factor and a Formal Calculation of Criticality 2.16 Fast Fission Factor Definition 2.17 Resonance Escape Probability 2.18 Group Collapsing 2.18.1 Multigroup Collapsing to One Group 2.18.2 Multigroup Collapsing to Two Group 2.18.3 Two Group Criticality 2.19 The Infinite Reactor 2.20 Finite Reactor 2.21 Time Dependence 2.22 Thermal Utilization Factor 2.23 References 2.24 Problems Chapter Three: Spatial Effects in Modeling Neutron Diffusion - One Group Models 3.0 Nuclear Reactor Calculations 3.1.1 Neutron Spectrum 3.2 Control Rods in Reactors 3.2.1 Lattice Calculation Analysis 3.3 An Introduction to Neutron Transport Equation 3.4 Neutron Current Density Concept in General 3.5 Neutron Current Density and Fick's Law 3.6 Problem Classification and Neutron Distribution 3.7 Neutron Slowing Down 3.8 Neutron Diffusion Concept 3.9 The One Group Model and One Dimensional Analysis 3.10.1 Boundary Conditions for the Steady-State Diffusion Equation 3.10.2 Boundary Conditions - Consistent and Approximate 3.10.3 An Approximate Methods for Solving the Diffusion Equation 3.10.4 The P1 Approximate Methods in Transport Theory 3.11 Further Analysis Methods for One Group 1 6.4 Summary of Slowing Down Equations 6.5 References 6.6 Problems Chapter Seven: Resonance Processing 7.0 Difficulties Presented by Resonance Cross Sections 7.1 What is Nuclear Resonance -- Compound Nucleus 7.1.1 Breit-Wigner Resonance Reaction Cross Sections 7.1.2 Resonance and Neutron Cross Section 7.2 Doppler Effect and Doppler Broadening of Resonance 7.3 Doppler Coefficient in Power Reactors 7.4 Infinite Resonance Integrals and Group Cross Section 7.4.1 The Flux Calculator Method 7.4.2 The Bondarenko Method - The Bondarenko Factor 7.4.3 The CENTRM Method 7.5 Infinite Resonance Integrals and Group Cross Sections 7.6 Dilution Cross Section - Dilution Factor 7.7 Resonance Effects 7.8 Homogeneous Narrow Resonance Approximation 7.9 Homogeneous Wide Resonance Approximation 7.10 Heterogeneous Narrow Resonance Approximation 7.11 Heterogeneous Wide Resonance Approximation 7.12 References 7.13 Problems Chapter Eight: Heterogeneous Reactors and Wigner Seitz Cells 8.0 Homogeneous and Heterogeneous Reactors 8.1 Spectrum Calculation in Heterogeneous Reactors 8.2 Cross Section Self Shielding and Wigner-Seitz Cells 8.3 References 8.4 Problems Chapter Nine: Thermal Spectra and Thermal Cross Sections 9.0 Coupling to Higher Energy Sources 9.1 Chemical Binding and Scattering Kernels 9.1.1 Scattering Materials 9.1.2 Thermal C
| Erscheinungsdatum | 23.09.2016 |
|---|---|
| Zusatzinfo | XXII, 551 p. 148 illus., 58 illus. in color. |
| Verlagsort | Cham |
| Sprache | englisch |
| Maße | 155 x 235 mm |
| Themenwelt | Naturwissenschaften ► Physik / Astronomie ► Atom- / Kern- / Molekularphysik |
| Technik ► Elektrotechnik / Energietechnik | |
| Schlagworte | Energy • Heterogeneous Reactors • Modeling Nuclear Plants • Neutron Diffusion • nuclear energy • Nuclear Engineering • Nuclear Fisson • Nuclear Physics, Heavy Ions, Hadrons • Nuclear power • nuclear reactor • Nuclear Reactor Stability • Reactor Neutronics |
| ISBN-13 | 9783319429625 / 9783319429625 |
| Zustand | Neuware |
| Informationen gemäß Produktsicherheitsverordnung (GPSR) | |
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