To provide a fast-breeder nuclear power generation system including a natural circulation type decay heat removal system device capable of surely preventing coagulation of sodium with excellent reliability.
The decay heat removal system device 28 includes a PRACS 25, an air cooler 26, and a decay heat removing system pipe 27 connecting the PRACS 25 to the air cooler 26. The pipe 27 includes a high-temperature pipe 27a for supplying high-temperature decay heat removing system coolant heated by the PRACS 25 to the air cooler 26 and a low-temperature pipe 27b for returning low-temperature decay heat removing system coolant cooled by the air cooler 26 to the PRACS 25. A heat pipe 31 including a condenser part 32, an evaporation part 33 and a heat insulation part 34 is set within the high-temperature pipe 27a with the condenser part 32 being turned to the air cooler 26.
NANBA KOJI
ITOOKA SATOSHI
KUMAGAI NAOKI
JP2002214381A | 2002-07-31 | |||
JPS58104997A | 1983-06-22 | |||
JPS588197A | 1983-01-18 | |||
JPS58118988A | 1983-07-15 | |||
JPH01174897A | 1989-07-11 |