2007The proceedings of the JSME annual meetingOpen access

0611 Development of an Advanced Fuel Subassembly for Non-refueling Core in FBR : Water Tests with Bundle Models

Satoshi Nishimura, Tomonari Koga, Shoichi Moriya, Izumi Kinoshita

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Abstract

4S (Super-Safe, Small and Simple) is a sodium cooled fast reactor with non-refueling core, aiming to play a local energy supplier. The core is very tall and has a dense arrangement of thick fuel pins in order to achieve a long life. Since previous thermal hydraulic data is limited to thin fuel pin bundles with larger pin-to-pin gap, we have conducted analytical and experimental studies focusing on the thermal hydraulics for such a unique fuel subassembly. The present paper addresses water tests with full bundle and partial bundle models.

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4S (Super-Safe, Small and Simple) is a sodium cooled fast reactor with non-refueling core, aiming to play a local energy supplier. The core is very tall and has a dense arrangement of thick fuel pins in order to achieve a long life. Since previous thermal hydraulic data is limited to thin fuel pin bundles with larger pin-to-pin gap, we have conducted analytical and experimental studies focusing on the thermal hydraulics for such a unique fuel subassembly. The present paper addresses water tests with full bundle and partial bundle models.

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Available abstract

4S (Super-Safe, Small and Simple) is a sodium cooled fast reactor with non-refueling core, aiming to play a local energy supplier. The core is very tall and has a dense arrangement of thick fuel pins in order to achieve a long life. Since previous thermal hydraulic data is limited to thin fuel pin bundles with larger pin-to-pin gap, we have conducted analytical and experimental studies focusing on the thermal hydraulics for such a unique fuel subassembly. The present paper addresses water tests with full bundle and partial bundle models.

Key concepts: Bundle, Thermal hydraulics, Hydraulics, Nuclear engineering, Core (optical fiber), Thermal, Engineering, Environmental science

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