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Engineering
Nuclear Engineering
Nuclear Reactor Physics and Design
1. Fundamentals of Nuclear and Neutron Physics
2. Neutron Transport and Diffusion Theory
3. Reactor Criticality and Neutron Balance
4. Reactor Kinetics and Control
5. Core Design and Fuel Management
6. Thermal-Hydraulics and Heat Transfer
7. Reactor Safety Analysis
8. Reactor Types and Design Concepts
Reactor Criticality and Neutron Balance
Neutron Life Cycle
Four-Factor Formula
Fast Fission Factor
Definition and Physical Meaning
Factors Affecting Fast Fission
Resonance Escape Probability
Resonance Absorption
Temperature Effects
Thermal Utilization Factor
Fuel-to-Moderator Ratio
Parasitic Absorption
Reproduction Factor
Neutrons per Absorption
Fuel Composition Effects
Six-Factor Formula
Fast Non-Leakage Probability
Fast Leakage
Core Size Effects
Thermal Non-Leakage Probability
Thermal Leakage
Geometric Effects
Multiplication Factor
Infinite Multiplication Factor
Effective Multiplication Factor
Critical Condition
One-Group Diffusion Model
Critical Equation
Material Buckling
Geometric Buckling
Critical Condition
Critical Size Calculations
Bare Reactor Geometries
Spherical Reactor
Cylindrical Reactor
Slab Reactor
Reflected Reactors
Reflector Savings
Critical Size Reduction
Neutron Flux Distribution
Fundamental Mode
Higher Harmonics
Flux Shapes in Different Geometries
Multi-Group Diffusion Theory
Group Structure
Energy Group Definition
Group Constants
Cross Section Averaging
Two-Group Model
Fast Group Equation
Thermal Group Equation
Group Coupling
Two-Group Critical Equation
Few-Group Methods
Group Condensation
Spectral Calculations
Homogenization Techniques
Heterogeneous Effects
Cell Calculations
Unit Cell Definition
Flux Disadvantage Factors
Cell-Averaged Cross Sections
Self-Shielding
Spatial Self-Shielding
Resonance Self-Shielding
Dancoff Correction
Double Heterogeneity
Fuel Particle Effects
Lattice Effects
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2. Neutron Transport and Diffusion Theory
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4. Reactor Kinetics and Control