Author:
Meng Xiangyu,Liu Yanbin,Wang Xuesheng,Cao Jiaming
Abstract
Abstract
The Passive Residual Heat Removal Heat Exchanger (PRHR HX) is an important equipment of the passive safety system in advanced nuclear power plants such as AP1000. Heat transfer phenomenon and characteristics study of the PRHR HX has received more and more attention. However, the research of transient heat transfer under C-shaped tube outside pool boiling condition is insufficient and needs further investigation. An experimental facility was built and a series of experiments were conducted. Distributing and changing tendencies of some important parameters including tank water temperature, tube wall temperature and heat transfer coefficient were obtained and analyzed. This study can provide a reference for the thermal hydraulic design for the PRHR HX in nuclear power plant.
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