Simplified SBLOCA Analysis of AP1000

Conference · Thu Jul 01 04:00:00 EDT 2004

OSTI ID:21160678

Brown, William L ^[1]

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1. Westinghouse Electric Company LLC, Pittsburgh, PA 15230 (United States)

The AP1000 is a 1000 MWe advanced nuclear power plant design that uses passive safety features such as a multi-stage, automatic depressurization system (ADS) and gravity-driven, safety injection from core make-up tanks (CMTs) and an in-containment refueling water storage tank (IRWST) to mitigate SBLOCA events. The period of most safety significance for AP1000 during a SBLOCA event is typically associated with the actuation of the fourth stage of the ADS and subsequent transition from CMT to IRWST safety injection. As this period of a SBLOCA is generally of a quasi-steady nature, the integral performance of the AP1000 can be understood and evaluated with a simplified model of the reactor vessel, ADS, and safety injection from the CMTs and IRWST. The simplified model of the AP1000 consists of a series of steady state simulations that uses drift flux in the core region and homogeneous treatment of the core exit region including the ADS flow paths to generate a family of core flow demand curves as a function of system pressure (i.e. mass flow required to satisfy core cooling). These core flow demand curves are plotted against passive safety system supply curves from the CMTs and IRWST to demonstrate the adequacy of the integral performance of the AP1000 during the most important phase of a SBLOCA. (author)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160678
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
AVAILABILITY
CONTAINMENT
COOLING
DEPRESSURIZATION SYSTEMS
DESIGN
DIAGRAMS
NUCLEAR POWER PLANTS
PERFORMANCE
REACTOR VESSELS
SAFETY
SAFETY INJECTION
STEADY-STATE CONDITIONS
TANKS
WATER