Water Test of Natural Circulation for Decay Heat Removal in JSFR
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

Tomonari Koga (CRIEPI)
Takahiro Murakami (CRIEPI)
Yuzuru Eguchi (CRIEPI)
Takaharu Matsuzawa (MFBR)
Osamu Watanaba (MFBR)


Japan Atomic Energy Agency (JAEA) is conducting a design study of Japan Sodium-cooled Fast Reactor (JSFR), in which a decay heat removal system (DHRS) utilizing natural circulation (NC) is applied as an innovative technology. The Central Research Institute of Electric Power Industry (CRIEPI) has carried out a water test to verify the applicability of NC to decay heat removal. The test used a 1/10-scale model of JSFR. Key issues on thermal-hydraulics were identified through simulation tests on representative events. Measures were also proposed to resolve these issues. The present study has demonstrated that a sufficient and stable NC is established in each event.

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