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 (17), even if fluid line breakage of a reactor pressure vessel (15) occurs and for whatever reason, supply of a coolant (2) to the reactor pressure vessel (15) fails.
This invention includes: a heat exchanger (1) provided at a position higher than a primary containment vessel (17); a condensate storage tank (5) disposed below the heat exchanger and above an upper end of a reactor core (13) placed in a reactor pressure vessel (15); a non-condensate gas discharge line (8) connected at a first end thereof to an upper section of the condensate storage tank (5) and at a second end thereof to a suppression pool (20); a second condensate discharge line (9) connected at a first end thereof to a position below that section of the condensate storage tank (5) to which the first end of the non-condensate gas discharge line (8) is connected, and at a second end thereof to the suppression pool (20); and a condensate return line (10) connected at a first end thereof to a position below that section of the condensate storage tank (5) to which the first end of the second condensate discharge line (9) is connected, and at a second end thereof to a side portion of the reactor pressure vessel (15), the side portion being above the upper end of the core (13).