Sodium Experiment on Fully Natural Circulation Systems for Decay Heat Removal in Japan Sodium-Cooled Fast Reactor
NURETH-14 - 2011 September 25-30

Presented at:
2011 September 25-30
Toronto, Canada
Session Title:
G1-1 - Sodium Cooled Fast Reactors Design and Safety and Lead/Lead-Bismuth Cooled Reactors

Hideki Kamide (Japan Atomic Energy Agency)
Jun Kobayashi (Japan Atomic Energy Agency)
Ayako Ono (Japan Atomic Energy Agency)
Nobuyuki Kimura (Japan Atomic Energy Agency)
Osamu Watanabe (MFBR)


Fully natural circulation system is adopted in a decay heat removal system (DHRS) of Japan Sodium Cooled Fast Reactor (JSFR).The DHRS of JSFR consists of one unit of DRACS (direct reactor auxiliary cooling system), which has a dipped heat exchanger in the reactor vessel and two units of PRACS, which has a heat exchanger in a primary-side inlet plenum of IHX in each loop.Sodium experiments were carried out for heat transfer characteristics of a sodium- sodium heat exchanger of PRACS and start-up transient of the DHRS loop with parameters of pressure loss coefficients in the loops.The transient experiments for the start-up of DHRS loop showed that quick increase of natural draft in the air duct followed by smooth increase of sodium flow rate in the DHRS loop.Influences of the pressure loss coefficients in the primary loop and the DHRS loop were limited on the core temperature and also heat removal of PRACS, respectively due to recovery of natural circulation head via the increase of temperature difference in each loop.

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