The PWR consists of a primary system (reactor system) and a secondary system (steam system) in order to keep radioactive materials in the primary system. The reactor coolant in a reactor vessel (reactor coolant) of the primary system is pressurized so that it circulates with reactor coolant pumps without boiling, and the high-temperature and high-pressure reactor coolant (reactor-vessel outlet temperature: about 325 degree-C, reactor-vessel inlet pressure: about 157 kg/cm2, at rated power) moves from a reactor core to steam generators (primary side) for effective heat transfer. Within the steam generators, heat exchange occurs at heat transfer tubestran sporting the heat from the primary side to the secondary side, and steam (operating temperature: about 277 degree-C and operating pressure: about 62 kg/cm2, at rated power) is generated. This steam is sent to a turbine to drive a generator, condensed in condensers to water, and sent back to the steam generators (secondary side) with main feedwater pumps (feedwater).
Nuclear Steam Supply System
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A PWR consists of the primary cooling system, chemical and volume control system, emergency core cooling system, container spray system, residual heat removal system, fuel handling system, waste processing system, turbine-generator system etc.