Safety instrument test facility (FITY) is one of the high temperature and high pressure test facilities in CGN. It is designed to conduct tests on thermal-hydraulic of safety system and instruments under the similar condition of reactor severe accident. FITY uses lot of copper components to realize sealing and insulation of vessel. Varies of hot state tests revealed that copper components worked well during the test, however, electrochemical corrosion was found as well, making water quality get worse. This article introduces chemical composition, physical properties and electrochemical corrosion behavior of copper component used in FITY, then analyzes the cause of corrosion and summarizes the notice for electronic component design under high temperature and high pressure conditions.
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2017 25th International Conference on Nuclear Engineering
July 2–6, 2017
Shanghai, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5780-9
PROCEEDINGS PAPER
Research on Corrosion Behavior of Copper in Reactor Thermal Hydraulic Test
Haiyan Xu,
Haiyan Xu
China Nuclear Power Technology Research Institute Co. Ltd., Shenzhen, China
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Donghua Lu,
Donghua Lu
China Nuclear Power Technology Research Institute Co. Ltd., Shenzhen, China
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Xiaohang Wu,
Xiaohang Wu
China Nuclear Power Technology Research Institute Co. Ltd., Shenzhen, China
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Qianhua Su
Qianhua Su
China Nuclear Power Technology Research Institute Co. Ltd., Shenzhen, China
Search for other works by this author on:
Haiyan Xu
China Nuclear Power Technology Research Institute Co. Ltd., Shenzhen, China
Donghua Lu
China Nuclear Power Technology Research Institute Co. Ltd., Shenzhen, China
Xiaohang Wu
China Nuclear Power Technology Research Institute Co. Ltd., Shenzhen, China
Qianhua Su
China Nuclear Power Technology Research Institute Co. Ltd., Shenzhen, China
Paper No:
ICONE25-67359, V002T03A096; 5 pages
Published Online:
October 17, 2017
Citation
Xu, H, Lu, D, Wu, X, & Su, Q. "Research on Corrosion Behavior of Copper in Reactor Thermal Hydraulic Test." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 2: Plant Systems, Structures, Components and Materials. Shanghai, China. July 2–6, 2017. V002T03A096. ASME. https://doi.org/10.1115/ICONE25-67359
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