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.
Skip Nav Destination
Article navigation
June 2015
Research-Article
An Assessment of Mechanical Properties of A508-3 Steel Used in Chinese Nuclear Reactor Pressure Vessels
Meifang Yu,
Meifang Yu
College of Material Science and Engineering,
e-mail: yumeifang999@sina.cn
Tianjin University
,92 Weijin Road
,Tianjin, China, 300072
e-mail: yumeifang999@sina.cn
Search for other works by this author on:
Y. J. Chao,
Y. J. Chao
1
Fellow ASME
College of Material Science and Engineering,
College of Material Science and Engineering,
Tianjin University
,92 Weijin Road
,Tianjin, China, 300072
Department of Mechanical Engineering,
e-mail: chao@sc.edu
University of South Carolina
,300 S. Main
,Columbia, SC 29208
e-mail: chao@sc.edu
1Corresponding author.
Search for other works by this author on:
Zhen Luo
Zhen Luo
College of Material Science and Engineering,
e-mail: lz@tju.edu.cn
Tianjin University
,92 Weijin Road
,Tianjin 300072
, China
e-mail: lz@tju.edu.cn
Search for other works by this author on:
Meifang Yu
College of Material Science and Engineering,
e-mail: yumeifang999@sina.cn
Tianjin University
,92 Weijin Road
,Tianjin, China, 300072
e-mail: yumeifang999@sina.cn
Y. J. Chao
Fellow ASME
College of Material Science and Engineering,
College of Material Science and Engineering,
Tianjin University
,92 Weijin Road
,Tianjin, China, 300072
Department of Mechanical Engineering,
e-mail: chao@sc.edu
University of South Carolina
,300 S. Main
,Columbia, SC 29208
e-mail: chao@sc.edu
Zhen Luo
College of Material Science and Engineering,
e-mail: lz@tju.edu.cn
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. Jun 2015, 137(3): 031402 (7 pages)
Published Online: June 1, 2015
Article history
Received:
August 31, 2014
Revision Received:
December 7, 2014
Online:
March 25, 2015
Citation
Yu, M., Chao, Y. J., and Luo, Z. (June 1, 2015). "An Assessment of Mechanical Properties of A508-3 Steel Used in Chinese Nuclear Reactor Pressure Vessels." ASME. J. Pressure Vessel Technol. June 2015; 137(3): 031402. https://doi.org/10.1115/1.4029434
Download citation file:
Get Email Alerts
Lateral and Transverse Stiffness Requirements for Supports of Pipeline Systems Conveying Fluids
J. Pressure Vessel Technol
Master Curve Evaluation Using the Fracture Toughness Data at Low Temperature of T − T0 < −50 °C
J. Pressure Vessel Technol (June 2025)
Investigation of the Dynamic Response of Soil/Steel Composite Structures of Vacuum Explosion Containment Vessels
J. Pressure Vessel Technol (June 2025)
Related Articles
Cost-Effective Alternatives to Conventional Charpy Tests for Measuring the Impact Toughness of Very-High-Toughness Steels
J. Pressure Vessel Technol (April,2018)
Brittle Fracture Prevention Model for Pressure Based on Master Curve Approach
J. Pressure Vessel Technol (February,2017)
Applicability of the ASME Exemption Curve for Chinese Pressure Vessel Steel Q345R
J. Pressure Vessel Technol (December,2015)
Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens
J. Pressure Vessel Technol (October,2015)
Related Chapters
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Repair Methods for Loadbearing Steel Structures Operating on the Norwegian Continental Shelf
Ageing and Life Extension of Offshore Facilities
Experience in Plane-Strain Fracture Toughness Testing Per ASTM Method E 399
Developments in Fracture Mechanics Test Methods Standardization