Abstract
In this paper, the operational characteristics of air-cooled type passive residual heat removal (PRHR) system of the nuclear heating reactor are studied with RELAP5 code. The PRHR uses the air natural circulation which can transfer heat directly from the reactor vessel to the air, and its heat transfer process is particularly important for the reactor safety. However, the current thermal–hydraulic code lacks the relevant air cooler model. A method how to model an air cooler is proposed based on the conservation equation and can be widely applied to different situations. Moreover, the operating characteristics of air cooling tower and the transient thermal–hydraulic characteristics of station blackout (SBO) event have been analyzed. The results show that the heat transfer coefficient of air cooler increases with the heat transfer power, and the inlet temperature has little influence on the heat transfer coefficient. The air cooling type PRHRS can transfer the core residual heat timely and continuously. There is a time delay of the heat exchanger power between the main heat exchanger and air cooler caused by the temperature distribution.
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