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Neutronic Analysis for Nuclear Reactor Systems

Neutronic Analysis for Nuclear Reactor Systems


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Table of ContentsAbout the Authors PrefaceAcknowledgmentChapter One: Neutron Physics Background1.0 Nuclei - Sizes, Composition, and Binding Energies1.1 Decay of a Nucleus1.2 Distribution of Nuclides and Nuclear Fission/Nuclear Fusion1.3 Neutron-Nucleus Interaction1.3.1 Nuclear Reactions Rates and Neutron Cross Sections1.3.2 Effects of Temperature on Cross Section1.3.3 Nuclear Cross Section Processing Codes1.3.4 Energy Dependence of Neutron Cross Sections1.3.5 Types of Interactions1.4 Mean Free Path1.5 Nuclear Cross Section and Neutron Flux Summary1.6 Fission1.7 Fission Spectra1.8 The Nuclear Fuel1.6.1 Fertile Material1.9 Liquid Drop Model of a Nucleus1.10 Summary of Fission Process1.11 Reactor Power Calculation1.12 Relationship between Neutron Flux and Reactor Power1.13 References1.14 ProblemsChapter Two: Modeling Neutron Transport and Interactions2.0 Transport Equations2.1 Reaction Rates2.2 Reactor Power Calculation2.3 Relationship between Neutron Flux and Reactor Power2.4 Neutron Slowing Down and Thermalization2.5 Macroscopic Slowing Down Power2.6 Moderate Ratio2.7 Integro-Differential Equation (Maxwell-Boltzmann Equation)2.8 Integral Equation2.9 Multigroup Diffusion Theory2.10 The Multigroup Equations2.11 Generating the Coefficients2.12 Simplifications2.13 Nuclear Criticality Concepts2.14 Criticality Calculation2.15 The Multiplication Factor and a Formal Calculation of Criticality2.16 Fast Fission Factor Definition2.17 Resonance Escape Probability2.18 Group Collapsing2.18.1 Multigroup Collapsing to One Group2.18.2 Multigroup Collapsing to Two Group2.18.3 Two Group Criticality2.19 The Infinite Reactor2.20 Finite Reactor2.21 Time Dependence2.22 Thermal Utilization Factor2.23 References2.24 ProblemsChapter Three: Spatial Effects in Modeling Neutron Diffusion - One Group Models3.0 Nuclear Reactor Calculations3.1.1 Neutron Spectrum3.2 Control Rods in Reactors3.2.1 Lattice Calculation Analysis3.3 An Introduction to Neutron Transport Equation3.4 Neutron Current Density Concept in General3.5 Neutron Current Density and Fick's Law3.6 Problem Classification and Neutron Distribution3.7 Neutron Slowing Down3.8 Neutron Diffusion Concept3.9 The One Group Model and One Dimensional Analysis3.10.1 Boundary Conditions for the Steady-State Diffusion Equation3.10.2 Boundary Conditions - Consistent and Approximate3.10.3 An Approximate Methods for Solving the Diffusion Equation3.10.4 The P1 Approximate Methods in Transport Theory3.11 Further Analysis Methods for One Group3.11.2 Cylindrical Geometry3.11.3 Spherical Geometry3.12 Eigenfunction Expansion Methods and Eigenvalue Equations3.12.1 Eigenvalues and Eigenfunctions Problems3.13 Multi-Dimensional Models and Boundary Conditions3.13.1 The Unreflected Reactor Parallelepiped Core3.13.2 The Minimum Volume of the Critical Parallelepiped3.13.3 The Peak to Average Flux Ratio3.13.4 The Finite Height Cylindrical Core3.14 Relating k to the Criticality Condition3.15 Analytical Solution for the Transient Case for Reactor3.16 Criticality3.17 Bare Critical Reactor 1-
About the Author: 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.


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Product Details
  • ISBN-13: 9783319827063
  • Publisher: Springer
  • Publisher Imprint: Springer
  • Height: 234 mm
  • No of Pages: 551
  • Spine Width: 30 mm
  • Width: 156 mm
  • ISBN-10: 3319827065
  • Publisher Date: 28 Jun 2018
  • Binding: Paperback
  • Language: English
  • Returnable: N
  • Weight: 843 gr


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