The valve stem used in the main steam system of nuclear power plant is usually 17-4PH martensitic stainless steel. When it served in 300 C° for a long time, the thermal aging embrittlement of valve stem will be significant, with the performance of the ductile brittle transition temperature (DBTT) and the hardness increased, the upper stage energy (USE) decreased. It will seriously affect the safety and economic operation of nuclear power plant (NPP). It is important to study the thermal aging effect of the 17-4PH steel for safe operation of nuclear power plant. In this work, Three-Dimensional Atom Probe (3DAP), Energy Dispersive X-Ray Spectroscopy (EDX), Scanning Electron Microscope (SEM) and Optical Microscope (OM) are used to analyze the element distribution in 17-4PH steel. The results show that lath martensite will grow significantly under high temperature for a long time. More δ-ferrite will be found between lath martensite, and some carbide aggregates at its interface. In addition, the number density of Cu clusters in the17-4PH steel is increased. It is found that Ni and Mn have obvious segregation with the Cu cluster.
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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
Effect of Element Segregation on Thermal Aging Behavior of 17-4PH Martensitic Stainless Steel for Nuclear Power Plant
Bing Bai,
Bing Bai
China Institute of Atomic Energy, Beijing, China
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Hanxiao Wang,
Hanxiao Wang
China Institute of Atomic Energy, Beijing, China
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Changyi Zhang,
Changyi Zhang
China Institute of Atomic Energy, Beijing, China
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Zhenfeng Tong,
Zhenfeng Tong
China Institute of Atomic Energy, Beijing, China
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Wen Yang
Wen Yang
China Institute of Atomic Energy, Beijing, China
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Bing Bai
China Institute of Atomic Energy, Beijing, China
Hanxiao Wang
China Institute of Atomic Energy, Beijing, China
Changyi Zhang
China Institute of Atomic Energy, Beijing, China
Zhenfeng Tong
China Institute of Atomic Energy, Beijing, China
Wen Yang
China Institute of Atomic Energy, Beijing, China
Paper No:
ICONE25-66977, V002T03A076; 4 pages
Published Online:
October 17, 2017
Citation
Bai, B, Wang, H, Zhang, C, Tong, Z, & Yang, W. "Effect of Element Segregation on Thermal Aging Behavior of 17-4PH Martensitic Stainless Steel for Nuclear Power Plant." Proceedings of the 2017 25th International Conference on Nuclear Engineering. Volume 2: Plant Systems, Structures, Components and Materials. Shanghai, China. July 2–6, 2017. V002T03A076. ASME. https://doi.org/10.1115/ICONE25-66977
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