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Research Papers: Materials and Fabrication

An Assessment of Mechanical Properties of A508-3 Steel Used in Chinese Nuclear Reactor Pressure Vessels

[+] Author and Article Information
Meifang Yu

College of Material Science and Engineering,
Tianjin University,
92 Weijin Road,
Tianjin, China, 300072
e-mail: yumeifang999@sina.cn

Y. J. Chao

Fellow ASME
College of Material Science and Engineering,
Tianjin University,
92 Weijin Road,
Tianjin, China, 300072
Department of Mechanical Engineering,
University of South Carolina,
300 S. Main,
Columbia, SC 29208 
e-mail: chao@sc.edu

Zhen Luo

College of Material Science and Engineering,
Tianjin University,
92 Weijin Road,
Tianjin 300072, China
e-mail: lz@tju.edu.cn

1Corresponding author.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received August 31, 2014; final manuscript received December 7, 2014; published online March 25, 2015. Assoc. Editor: Marina Ruggles-Wrenn.

J. Pressure Vessel Technol 137(3), 031402 (Jun 01, 2015) (7 pages) Paper No: PVT-14-1140; doi: 10.1115/1.4029434 History: Received August 31, 2014; Revised December 07, 2014; Online March 25, 2015

China has very ambitious goals of expanding its commercial nuclear power by 30 GW within the decade and wishes to phase out fossil fuels emissions by 40–45% by 2020 (from 2005 levels). With over 50 new nuclear power plants under construction or planned and a design life of 60 years, any discussions on structural integrity become very timely. Although China adopted its nuclear technology from France or USA at present time, e.g., AP1000 of Westinghouse, the construction materials are primarily “Made in China.” Among all issues, both the accumulation of the knowledge base of the materials and structures used for the power plant and the technical capability of engineering personnel are imminent. This paper attempts to compile and assess the mechanical properties, Charpy V-notch impact energy, and fracture toughness of A508-3 steel used in Chinese nuclear reactor pressure vessels (RPVs). All data are collected from open literature and by no means complete. However, it provides a glimpse into how this domestically produced steel compares with western RPV steels such as USA A533B and Euro 20MnMoNi55.

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Figures

Grahic Jump Location
Fig. 1

Tensile and yield strength of Chinese A508-3 steel

Grahic Jump Location
Fig. 2

True stress–strain curve of Chinese A508-3 steel and A533B at −15 °C

Grahic Jump Location
Fig. 3

Charpy V-notch energy of Chinese A508-3 [14,16,21,27-30], USA A533B [31-35], and Euro 20MnMoNi55 [36-39]

Grahic Jump Location
Fig. 4

Charpy absorbed energy–temperature curve of Chinese A508-3 steel, USA A533B and Euro 20MnMoNi55 steel; Eqs. (5)–(6)

Grahic Jump Location
Fig. 5

Fracture toughness KIC of Chinese A508-3 steel, USA A533B, Euro 22NiMoCr37, and Euro 20MnMoNi55 as a function of temperature

Grahic Jump Location
Fig. 6

Fracture toughness KIC of three Chinese A508-3 steels(A64, B78, C87) [19]

Grahic Jump Location
Fig. 7

Fracture Toughness KIC of Chinese A508-3 steel, USA A533B, and Euro 20MnMoNi55 steels scaled by T-RTNDT

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