Validation of a plant dynamics code for 4S - Test analysis of natural circulation behavior

Conference · Sun Jul 01 04:00:00 EDT 2012

OSTI ID:22106002

Sebe, F.; Horie, H.; Matsumiya, H. ^[1]; Fanning, T. H. ^[2]

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1. Toshiba Corporation, 8 Shinsugita-Cho, Isogo-Ku, Yokohama, 235-8523 (Japan)
2. Argonne National Laboratory, 9700 S Cass Ave, Argonne, IL 60439 (United States)

A plant transient dynamics code for a sodium-cooled fast reactor was developed by Toshiba. The code is used to evaluate the safety performance of Super-Safe, Small, and Simple reactor (4S) for Anticipated Operational Occurrences (AOOs), Design Basis Accident (DBA) and Beyond DBA (BDBA). The code is currently undergoing verification and validation (V and V). As one of the validation, test analysis of the Shutdown Heat Removal Test (SHRT)-17 performed in the Experimental Breeder Reactor (EBR)-II was conducted. The SHRT-17 is protected loss of flow test. The purpose of this validation is to confirm capability of the code to simulate natural circulation behavior of the plant. As a result, good agreements are shown between the analytical results and the measured data which were available from instrumented subassembly. The detailed validation result of the natural circulation behavior is described in this paper. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22106002
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AFTER-HEAT REMOVAL
COMPUTER CODES
DESIGN BASIS ACCIDENTS
EBR-2 REACTOR
LOSS OF FLOW
NATURAL CONVECTION
REACTOR KINETICS
REACTOR SAFETY
REACTOR SHUTDOWN
VALIDATION