1996•Transactions of the American Nuclear SocietyRequires access

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

Richard F. Wright, L.E. Hochreiter, Mark Friend

Abstract

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.

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Key concepts: Nuclear engineering, Heat exchanger, Natural circulation, Coolant, Decay heat, Environmental science, Loss-of-coolant accident, Heat transfer