Abstract
Safety systems play a key role in the nuclear industry. In the past decades, various safety systems have been designed and built to enhance safety level in nuclear power plants. The advanced secondary passive residual heat removal system (ASP) is one of several passive safety systems designed to ensure the safety of the reactor core. Experimental study on transient and steady-state characteristics as well as relevant influence factors of ASP system were conducted by using the high temperature high pressure thermal-hydraulic test facility. The results showed that the C-type heat exchanger could effectively remove the residual heat, and get stronger with the increase of loop pressure. The results also showed natural circulation could be set up with good stability, and get little influence from movement of isolating valves, relief valve as well as water volume in steam generator. Besides, to certificate the reasonability and reliability of the ASP system directly, an integral test was conducted.
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