PASSIVE RESIDUAL HEAT REMOVAL SYSTEM AND NUCLEAR POWER PLANT EQUIPMENT

摘要

Disclosed is a passive residual heat removal system and nuclear power plant equipment configured to alleviate a rise in an internal pressure of a primary containment vessel, even if fluid line breakage of a reactor pressure vessel occurs and for whatever reason, supply of a coolant to the reactor pressure vessel fails. This invention includes: a heat exchanger provided at a position higher than a primary containment vessel; a condensate storage tank disposed below the heat exchanger and above an upper end of a reactor core placed in a reactor pressure vessel; a non-condensate gas discharge line connected at a first end thereof to an upper section of the condensate storage tank and at a second end thereof to a suppression pool; a second condensate discharge line connected at a first end thereof to a position below that section of the condensate storage tank to which the first end of the non-condensate gas discharge line is connected, and at a second end thereof to the suppression pool; and a condensate return line connected at a first end thereof to a position below that section of the condensate storage tank to which the first end of the second condensate discharge line is connected, and at a second end thereof to a side portion of the reactor pressure vessel, the side portion being above the upper end of the core.