Power generation inside homogenous and heterogeneous
reactor cores – 1-D and 2-D heat
conduction in nuclear fuel elements – numerical solutions of steady state and
transient problems (use of available codes such as FEM2D) - thermal shields - heat transfer by convection – selection
criteria for reactor coolants - heat transfer with change in phase – boiling
channel analysis - calculation of the pressure drops in pressurized and boiling
channels - critical flow – thermal reactor core design (hot channel (spot)
factor) – use of available thermal
analysis codes such as MITH, TH1, BWR and MIGHT. Power Generation in Nuclear
Reactor Cores: Energy Released in Fission, the fission energy in reactors, the
fissionable fuel density, the fission cross section in reactors. Heat
Generation in Reactors, (heat production in fuel elements, radiation heating,
and fission product decay), The total heat generated in core ( the Homogeneous core, the Heterogeneous core),
Reactor shutdown heat generation. Heat Removal From Nuclear Reactor 3General
Thermodynamic Considerations. Heat Flow by conduction: The Equations of Heat
Conduction for Fuel, Clad, Gap ( in Plate-type Fuel Elements, in Cylindrical
Fuel Element, in Spherical Shape Fuel element), Space-dependent Heat sources,
Heat Transfer to Coolants: Total Heat Produced in Fuel Element. Forced
Convection Heat Transfer In Single-Phase Coolants: Hydraulic Flow in Channels,
Heat transfer Coefficient (Equivalent Diameter of the Coolant Channel, Reynolds
Number, Nusselt Number Nu, Prandtle Pr). Axial Temperature Distributions:
Temperature of the Coolant as Function of Position along the Hottest Channel
and other Channels, Temperature of the Clad, Gap and Fuel as Function of
Position along the Hottest Channel and Other Channels, Determine the Maximum
Values of Temperatures Within the Fuel Rod and Their Positions (fuel, Gap and
Clad). Boiling Heat Transfer in Nuclear Reactors: Boiling Regimes: No Boiling,
Nucleate Boiling, Partial Film Boiling, Full film Boiling, Flow Patterns in a
Vertical Heated Channel, Correlation Used to Compute Heat Flux for Nucleate
Boiling). Two-phase Flow, Heat Addition to Boiling Flow, Axial Temperature
Distributions. Boiling Crisis: DNB, Critical heat flux CHF, Correlation to
Compute the CHF. Hydrodynamic Core Analysis: Single-phase Coolant Pressure
Drops. Boiling Channel Pressure Drops. Thermal-Hydraulic Core Analysis: DNB
ratio, Hot Channel Factors, Nuclear Hot Channel Factor, Engineering hot channel
Factor FE, Enthalpy-rise Hot Channel Factor, Determination Core
Size. Thermal-Hydraulic Design Codes. use of available thermal analysis codes
such as MITH, TH1, BWRand MIGHT.
