MATEC Web Conf.
Volume 207, 2018International Conference on Metal Material Processes and Manufacturing (ICMMPM 2018)
|Number of page(s)||8|
|Published online||18 September 2018|
The FAC Experimental Research on Vapor-water Two-phase Flow Piping System of CAP1400 Secondary Loop
State Nuclear Electric Power Planning Design & Research Institute Co., Ltd, Beijing 100095, China
2 School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China
a Corresponding author: email@example.com
CAP1400 power plant is one of the advanced Third-generation Pressurized Water Reactor power plant. To ensure the safety and stability of the power plant secondary loop during operation, the corrosion characteristic of CAP1400 secondary loop should been investigated. This paper set up a test facility to study the vapor-water two-phase flow corrosion status, which could be seen in the piping system after the control valve of heater drain line. The key parameters, such as pressure drop, temperature, and surface topography have been observed and measured, and the different corrosion characteristic in straight pipe, elbow, tee, and reducer also have been acquired in the tests. The test results and analysis could provide the basis for the corrosion resistance design of the drain pipelines in the CAP1400 nuclear power plant.
© The Authors, published by EDP Sciences, 2018
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