Reliability improvement of JSFR emergency power supply system

Nabeshima, Kunihiko  ; Aizawa, Kosuke ; Chikazawa, Yoshitaka  ; Sato, Daisuke*; Ikari, Risako*

One of the advantages in features of Japan Sodium-cooled Fast Reactor (JSFR) is that it's free from high-capacity power load or quick activation of emergency power supply because Decay Heat Removal System (DHRS) adopted natural circulation. However, the Emergency Power Supply System of JSFR is reconsidered to improve the reliability for station blackout (SBO) caused by extreme external events after the nuclear accident at Fukushima. A non-class 1E GTG are added for practically elimination of Loss of Heat Removal System (LOHRS), and alternative power supply system composed of small air-cooled DG and lead-acid batteries is newly introduced to maintain class 1E equipment against the long-term station blackout (SBO).