Neutronic Analysis for Nuclear Reactor Systems. ([2019])

• Record Type: Book
• Further Information: Note: Bahman Zohuri.
• Authors: Zohuri, Bahman
• Contents: Intro; Preface; Acknowledgment; Contents; About the Author; Chapter 1: Neutron Physics Background; 1.1 Nuclei: Sizes, Composition, and Binding Energies; 1.2 Decay of a Nucleus; 1.3 Distribution of Nuclides and Nuclear Fission/Nuclear Fusion; 1.4 Neutron-Nucleus Interaction; 1.4.1 Nuclear Reactions Rates and Neutron Cross Sections; 1.4.2 Effects of Temperature on Cross Section; 1.4.3 Nuclear Cross-Sectional Processing Codes; 1.4.4 Energy Dependence of Neutron Cross Sections; 1.4.5 Types of Interactions; 1.5 Mean Free Path; 1.6 Nuclear Cross Section and Neutron Flux Summary; 1.7 Fission 1.8 Fission Spectra 1.9 The Nuclear Fuel; 1.9.1 Fertile Material; 1.10 Liquid Drop Model of a Nucleus; 1.11 Summary of Fission Process; 1.12 Reactor Power Calculation; 1.13 Relationship Between Neutron Flux and Reactor Power; Problems; References; Chapter 2: Modeling Neutron Transport and Interactions; 2.1 Transport Equations; 2.2 Reaction Rates; 2.3 Reactor Power Calculation; 2.4 Relationship Between Neutron Flux and Reactor Power; 2.5 Neutron Slowing Down and Thermalization; 2.6 Macroscopic Slowing Down Power; 2.7 Moderate Ratio; 2.8 Integrodifferential Equation (Maxwell-Boltzmann Equation) 2.23 Thermal Utilization Factor f Problems; References; Chapter 3: Spatial Effects in Modeling Neutron Diffusion: One-Group Models; 3.1 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 Fickś 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 3.9.1 Boundary Conditions for the Steady-State Diffusion Equation 3.9.2 Boundary Conditions: Consistent and Approximate; 3.9.3 An Approximate Method for Solving the Diffusion Equation; 3.9.4 The P1 Approximate Methods in Transport Theory; 3.10 Further Analysis Methods for One Group; 3.10.1 Slab Geometry; 3.10.2 Cylindrical Geometry; 3.10.3 Spherical Geometry; 3.11 Eigenfunction Expansion Methods and Eigenvalue Equations; 3.11.1 Eigenvalues and Eigenfunctions Problems; 3.12 Multidimensional Models and Boundary Conditions; 3.12.1 The Unreflected Reactor Parallelepiped Core
• Edition: Second edition
• Publisher Details: Cham, Switzerland : Springer
• Publication Date: 2019
• Extent: 1 online resource (659 pages)
• Subjects: 621.48/3; Nuclear reactors; Nuclear reactors; Electronic books
• Languages: English
• ISBNs: 9783030049065
• Related ISBNs: 303004906X; 9783030049058
• Notes: Note: Description based on online resource; title from digital title page (viewed on March 13, 2019).
• Access Rights: Legal Deposit; Only available on premises controlled by the deposit library and to one user at any one time; The Legal Deposit Libraries (Non-Print Works) Regulations (UK).
• Access Usage: Restricted: Printing from this resource is governed by The Legal Deposit Libraries (Non-Print Works) Regulations (UK) and UK copyright law currently in force.