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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
Thermal-Hydraulics and Heat Transfer
Heat Generation in Reactor Core
Fission Energy Distribution
Energy per Fission
Spatial Distribution
Time Dependence
Decay Heat
Fission Product Decay
Actinide Decay
Time-Dependent Decay Heat
Neutron and Gamma Heating
Neutron Kinetic Energy Deposition
Gamma Ray Absorption
Heating in Non-Fuel Materials
Heat Transfer in Fuel Elements
Heat Conduction in Fuel
Thermal Conductivity
Temperature Distribution
Fuel Centerline Temperature
Gap Heat Transfer
Gap Conductance
Gas Gap Effects
Contact Conductance
Heat Transfer to Coolant
Convective Heat Transfer
Heat Transfer Coefficients
Surface Temperature
Coolant Flow and Heat Removal
Single-Phase Flow
Forced Convection
Natural Circulation
Flow Distribution
Two-Phase Flow
Boiling Heat Transfer
Flow Regimes
Void Fraction
Heat Transfer Correlations
Nusselt Number Correlations
Friction Factor Correlations
Two-Phase Correlations
Thermal Limits and Safety Margins
Critical Heat Flux
DNB Correlations
CHF Mechanisms
Safety Factors
Fuel Temperature Limits
Melting Point
Centerline Temperature Limit
Cladding Temperature Limits
Thermal Design Criteria
Departure from Nucleate Boiling Ratio
Linear Heat Generation Rate
Peak Cladding Temperature
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5. Core Design and Fuel Management
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7. Reactor Safety Analysis