Electron beam welding of oxide dispersion strengthened 9 Cr martensitic steel-an experimental and theoretical perspective

被引:0
作者
Kavithaa, S. [1 ]
Shaji, Salvin George [2 ]
Bhandiwad, Vijet [1 ]
机构
[1] Cent Mfg Technol Inst, Tumkur Rd, Bangalore 560022, Karnataka, India
[2] Karunya Inst Technol & Sci, Coimbatore 641114, Tamil Nadu, India
关键词
EBW; ODS; HIP; ACTIVATION STEEL; MICROSTRUCTURE; DAMAGE; POWER;
D O I
暂无
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Advanced nuclear energy systems present significant improvements in economics, safety, reliability and sustainability over currently operating reactor technologies. Proper choices of cladding and structural material with a. high neutron damage resistance b. good mechanical properties at high operating temperatures and c. low activation properties are essential for the safe and reliable operation of the system. The 9-12% Cr transformable steels with lower carbon (similar to 0.1%) contents and addition of Mo, W, V, Nb present better high temperature strength than austenitic steels. The use of 9%Cr steel is considered as an optimum solution taking into consideration the present day requirements like environment, efficiency, elasticity, experience and economy that dominate considerations of modern power station design, layout, fabrication and operation. The pursuit of improved efficiency/power plant performance resulted in the design of system operating at higher temperature and pressure, which requires materials with appropriate high-temperature mechanical properties and metallurgical stability at operating temperatures. Oxide Dispersion Strengthened (ODS) 9% Cr steels have the potential to advance the high temperature performance of associated components in advanced nuclear energy systems with marginal oxidation resistance. The research focuses on Electron beam welding (EBW) of Hot Isostatically Pressed (HIP) ODS 9 Cr martensitic steel in as-received condition to arrive at the optimized weld process parameters. The weldments were characterized using Optical Microscopy for depth of penetration and width of weldments. The experimental results were theoretically verified using Minitab software. (C) 2019 Elsevier Ltd. All rights reserved.
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页码:2509 / 2519
页数:11
相关论文
共 29 条
[1]  
Baluc N.L., 2006, P FUS EN C CHENGD CH, pOV/5
[2]   Materials to deliver the promise of fusion power - progress and challenges [J].
Bloom, EE ;
Zinkle, SJ ;
Wiffen, FW .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :12-19
[3]   Microstructural examination of oxide layers formed on an oxide dispersion strengthened ferritic steel exposed to supercritical water [J].
Chen, Yun ;
Sridharan, Kumar ;
Allen, Todd R. ;
Ukai, Shigeharu .
JOURNAL OF NUCLEAR MATERIALS, 2006, 359 (1-2) :50-58
[4]  
CORWIN W.R., 2006, NUCL ENG TECHNOL, V38, P591
[5]   Effect of HIP Temperature and Cooling Rate on Microstructure and Hardness of Joints for ODS-RAFM Steels and JLF-1 Steel [J].
Fu, Haiying ;
Nagasaka, Takuya ;
Muroga, Takeo ;
Kimura, Akihiko ;
Ukai, Shigeharu .
PLASMA AND FUSION RESEARCH, 2016, 11 (Specialissue1)
[6]   Irradiation response in weldment and HIP joint of reduced activation ferritic/martensitic steel, F82H [J].
Hirose, T. ;
Sokolov, M. A. ;
Ando, M. ;
Tanigawa, H. ;
Shiba, K. ;
Stoller, R. E. ;
Odette, G. R. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) :S557-S561
[7]  
Hirose T, 2010, PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE 2010, VOL 1: CODES AND STANDARDS, P263
[8]   Joining of 14YWT and F82H by friction stir welding [J].
Hoelzer, D. T. ;
Unocic, K. A. ;
Sokolov, M. A. ;
Feng, Z. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 442 (1-3) :S529-S534
[9]  
Jan Vit, 2017, Materials Science Forum, V891, P185, DOI 10.4028/www.scientific.net/MSF.891.185
[10]  
Klueh R. L., 2001, ASTM Monograph, V3