Nuclear Reactor Thermal-Hydraulics & Safety
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Nuclear Reactor Thermal-Hydraulics & Safety
Course Overview

 This course is concerned with thermal hydraulic analysis of the process systems that are required to transport heat energy away from the nuclear reactor source and transform this heat energy into useful work (generallyelectrical energy).
 Nuclear systems design is guided by analysis results.
 Analysis, in turn, is performed on a specific design to determine its performance.
Design and analysis of the reactor process involves a number of interrelated systems:
Reactor core, heat transport system. steam generators. Turbines, pressure control system ,coolant inventory control systems ,power control systems;
Number of system components:
Valves, pumps ,pipes ,vessels ,heat exchangers;
And number of engineering and science disciplines:
Reactor physics, Heat transfer, Fluid mechanics, Thermodynamics, Chemistry, Metallurgy, Control,
Stress analysis.
Heat Transport System (HTS)
 The heat transport system (HTS) is of central importance since it is the interface between the heat source and the heat sink.
 Good HTS performance is essential to reactor integrity, plant performance and safety.
 This course is primarily about the interplay the two main actors in hydraulic systems: flow and pressure.
 But because we are dealing with systems involving the transfer of heat, local density and enthalpy determine the pressure.
 Hence, thermal hydraulic system behaviour is largely determined by the simultaneous solution of the equations that govern these four variables (flow, pressure, density and enthalpy).
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