Passive safeguards design optimization studies for the Westinghouse AP600

Conference · Wed Nov 01 00:00:00 EST 1989 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5417659

Vertes, C M ^[1]

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1. Westinghouse Electric Corporation, Pittsburgh, PA (USA)

The loss-of-coolant accident (LOCA) represents the design-basis event to verify the adequacy of nuclear plant emergency core-cooling systems (ECCS). An ECCS performance analysis that demonstrates compliance with the final acceptance criteria of 10CFR50.46 of the Code of Federal Regulations must be submitted for each licensed U.S. light water reactor facility. The ECCS performance analyses that demonstrate compliance with the 10CFR50.46 final acceptance criteria have been performed for the unique Westinghouse AP600 advanced pressurized water reactor. The AP600 plant design features a low-power density core, passive safeguards systems (PSSs), canned-motor reactor coolant pumps, and an automatic depressurization system (ADS). Small-break LOCA analyses performed using the Westinghouse NOTRUMP evaluation model exhibited successful depressurization with no core uncovery. To optimize the AP600 passive safeguards systems, additional small-break LOCA analyses have been performed with the TREAT (transient real-time engineering analysis tool) code. The analyses performed were directed at determining the required PSS performance and optimum valve sizing and sequencing of the ADS, which would continue to exhibit no core uncovery during a small-break LOCA event.

• OSTI ID: 5417659
• Report Number(s): CONF-891103-; CODEN: TANSA; TRN: 91-024633
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 60; Conference: Winter meeting of the American Nuclear Society (ANS) and nuclear power and technology exhibit, San Francisco, CA (United States), 26-30 Nov 1989; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
T CODES
WESTINGHOUSE STANDARD REACTOR
ENGINEERED SAFETY SYSTEMS
REACTOR SAFETY
DEPRESSURIZATION
DESIGN
ECCS
HEAT TRANSFER
HYDRAULICS
PERFORMANCE
PIPES
REACTOR ACCIDENTS
REACTOR CORES
REACTOR LICENSING
REGULATIONS
RUPTURES
VALVES
ACCIDENTS
COMPUTER CODES
CONTROL EQUIPMENT
ENERGY TRANSFER
EQUIPMENT
FAILURES
FLOW REGULATORS
FLUID MECHANICS
LICENSING
MECHANICS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled