Nuclear Series
"Reactor Core Heat transfer"
Aims :
- The Aims of this title is to consider the roles of conduction and convection in the removal of primary heat from the nuclear fuel and the transfer of heat from primary to secondary coolants.
Objectives :
By the end of this course the student will be able to:
- State the temperature limits for fuel, cladding and primary coolant for Magnox, AGR and PWR designs and briefly describe their origins.
- State the process governing the transfer of heat within nuclear fuel.
- Describe the radial temperature profile across a fuel element for Magnox, AGR and PWR designs and state how the profile influences fuel element design.
- State the process governing the transfer of heat from the nuclear fuel element to the primary coolant during normal operations.
- Describe the flow regimes involved in the transfer of heat from a nuclear fuel element to the primary coolant during normal operations and state the heat transfer process within each regime.
- State the factors affecting the Heat Transfer Coefficient (h).
- List the factors affecting the Heat Transfer Coefficient (h) in order of their effect.
- Explain the effects of finning and surface roughening on the heat transfer from a fuel element to the primary coolant.
- State the advantages and disadvantages of finning and surface roughening.
- Sketch the axial temperature profile in a fuel channel for fuel, cladding and coolant and identify the position of the maximum in each case.
- State the relevance of this for reactor instrumentation.
- Explain the need for variable gagging for AGR and Magnox Reactor designs and describe briefly how this is achieved in each case.
- State the three sources of pressure drop a coolant circuit and relate the pressure drop to the coolant velocity for turbulent flow.
- Explain the balance between heat transfer and circulator power and the dependence of circulator power on boiler outlet temperature (T1).
Course Modules:
 Introduction
Operational Temperature Limits
Heat Transport in Nuclear Fuel
Heat Transfer from Nuclear Fuel to Primary Coolant
The Effect of Finning and Surface Roughening
Axial Power and Temperature Profiles In a Fuel Channel
Radial Heat Generation Profile Across The Reactor
Pressure Loss in the Primary Coolant Circuit
Circulator Power (Pumping Power)
Assessment
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The average course completion time is one hour 45 minutes.
