Experimental study of primary and secondary side coupling natural convection heat transfer characteristics of the passive residual heat removal system in AP1000

2021 ◽  
Author(s):  
Zhimin Qiu ◽  
Daogang Lu ◽  
Jingpin Fu ◽  
Li Feng ◽  
Yuhao Zhang
Keyword(s):  
Convection Heat Transfer ◽  
Heat Removal ◽  
Natural Convection Heat Transfer ◽  
Convection Heat ◽  
Heat Transfer Characteristics ◽  
Heat Removal System ◽  
Secondary Side ◽  
Removal System ◽  
Residual Heat ◽  
Side Coupling

Experimental Study on Natural Convection Heat Transfer Outside Tube Bundle in Space Under Low Temperature Difference

2020 ◽  
Author(s):  
Junxiu Xu ◽  
Ming Ding ◽  
Changqi Yan ◽  
Guangming Fan
Keyword(s):  
Heat Transfer ◽  
Heat Exchanger ◽  
Low Temperature ◽  
Tube Bundle ◽  
Convection Heat Transfer ◽  
Heat Removal ◽  
Natural Convection Heat Transfer ◽  
Convection Heat ◽  
Reactor Pool ◽  
Residual Heat

Abstract The Passive Residual Heat Removal System (PRHRS) is very important for the safety of the heating reactor after shutdown. PRHRS is a natural circulation system driven by density difference, therefore, the heat transfer performance of the Passive Residual Heat Removal Heat Exchanger (PRHR HX) has a great impact to the heat transfer efficiency of PRHRS. However, the most research object of PRHR HX is the C-shape heat exchanger at present, which located in In-containment Refueling Water Storage Tank (IRWST). This heat exchanger is mainly used for the PRHRS of nuclear power plants. In the swimming pool-type low-temperature heating reactor (SPLTHR), the PRHR HX is placed in the reactor pool, which the pressure and temperature of the reactor pool are relatively low, and the outside heat transfer mode of tube bundle is mainly natural convection heat transfer. In this study, a miniaturized single-phase pool water cooling system was built to investigate the natural convective heat transfer coefficient of the heat exchanger under the large space and low temperature conditions. The experimental data had been compared with several correlations. The results show that the predicted value of Yang correlation is the closest to the experimental data, which the maximum deviation is about 11%.

Study of the Tank Set of the PRHR on SG Secondary Side

2016 ◽  
Author(s):  
Ran Xu
Keyword(s):  
Steam Generator ◽  
Heat Removal ◽  
Engineering Practice ◽  
Water Tank ◽  
Plant Design ◽  
Station Blackout ◽  
Heat Removal System ◽  
Secondary Side ◽  
Removal System ◽  
Residual Heat

Passive systems are widely used in nuclear power plants, to enhance the inherent safety of the plant. Especially in the accident of station blackout, Passive Residual Heat Removal system (PRHR) which is installed on the secondary side of steam generator (SG), highly resolved the problem of the residual heat removal after reactor trip. The plant safety is improved largely by PRHR, this is the trend of the new plant design. A water tank is commonly mounted on the passive residual heat removal system (PRHR) of steam generator secondary side, which heavily impacts the performance and the startup procedure of PRHR. Moreover, there are many different types of tank layout in various plants design. Therefore it is necessary to study the thermal hydraulic feature of the different type the PRHR tank set. In this paper, the station blackout accident is chosen to verify the performance of the tank set. Then the assessment criteria of PRHR is established from a thermal hydraulic perspective. RELAP5/mod3.2 is adopted to simulate the accident. Based on the performance comparison of different tank sets, the best tank layout is selected, which is selected for the engineering practice. At last, the comparison of the predicted results and the test data is done to verify the performance of selected tank set design.

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