Passive heat removal in the AP600 for LOCA and non-LOCA events

Journal Article · Tue Dec 31 04:00:00 EST 1996 · Transactions of the American Nuclear Society

OSTI ID:436964

Wright, R F; Hochreiter, L E ^[1]; Friend, M T ^[2]

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1. Westinghouse Electric Corp., Pittsburgh, PA (United States)
2. Nuclear Electric Co., Gloucestershire (United Kingdom)

The AP600 reactor is a pressurized water reactor being designed to utilize a natural circulation heat exchanger as one of the safety-grade means of removing primary system heat following certain design-basis events. The passive residual heat removal (PRHR) heat exchanger removes primary system heat to mitigate loss-of-coolant-accident (LOCA) and non-LOCA events and functionally replaces the safety-grade auxiliary feed-water system used in current operating plants. Tests were performed to characterize the PRHR heat exchanger performance and to provide a basis for heat transfer correlations to be used in the safety analysis of the AP600.

• OSTI ID: 436964
• Report Number(s): CONF-9606116--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
DESIGN
ENGINEERED SAFETY SYSTEMS
HEAT EXCHANGERS
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR COOLING SYSTEMS
REACTOR SAFETY