Reactor Coolant System
The reactor coolant system of the PWR nuclear power plant consists of a reactor vessel, steam generators, reactor coolant pumps, a pressurizer, and other elements. These major components are connected by the reactor coolant piping to form a loop configuration.
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Reactor Vessel
The reactor vessel consists of fuel and core support structures, and designed to form a reactor coolant pressure
boundary withstanding high temperatures and high pressures during normal operation, abnormal transient condition,
and fast-neutron embrittlement.
Steam Generator
The steam generator is a vertical U-tube heat exchanger that converts the thermal energy generated in the
reactor vessel to the steam, and transfer the steam to the turbine system. The steam generator is located
higher than the inlet-outlet nozzles of the reactor vessel to enable the removal of decay heat by natural
circulation after the reactor shutdown.
Reactor Coolant Pump
The reactor coolant pump circulates the reactor coolant, to remove heat from the reactor core at a constant flow rate.
Pressurizer
The pressurizer controls the reactor coolant system pressure constant, actuating electrical heater, spray valve, and relief valve.
Reactor Coolant System
The reactor coolant piping inter-connects the reactor vessel, steam generator, and reactor coolant pump in
a circulating loop configuration.
| 600MWe Class | 900MWe Class | 1,200MWe Class | APWR1,500MWe Class | |
|---|---|---|---|---|
| Number of Loop | 2 | 3 | 4 | 4 |
| Operating Pressure(MPa) | Approx. 15.5 | Approx. 15.5 | Approx. 15.5 | Approx. 15.5 |
| Operating Temperature(°C) | Approx. 300 | Approx. 300 | Approx. 300 | Approx. 300 |
Business contact: Nuclear Energy Systems Nuclear Energy Systems Administration Department Planning Group +81-3-6716-4812
