Enhanced strength and high temperature resistance of 25Cr20Ni ODS austenitic alloy through thermo-mechanical treatment and addition of Mo

被引:17
作者
Zhou, Zhangjian [1 ]
Sun, Shengying [1 ]
Zou, Lei [1 ]
Schneider, Yanling [2 ]
Schmauder, Siegfried [2 ]
Wang, Man [1 ]
机构
[1] Univ Sci & Technol Beijing, Sch Mat Sci & Engn, Beijing 100083, Peoples R China
[2] Univ Stuttgart, Inst Mat Testing Mat Sci & Strength Mat IMWF, D-70569 Stuttgart, Germany
关键词
ODS; 310 austenitic alloy; Microstucture; Tensile property; MECHANICAL-PROPERTIES; MICROSTRUCTURE; STEELS;
D O I
10.1016/j.fusengdes.2018.11.020
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A Mo alloyed Oxide Dispersion Strengthened (ODS) austenitic alloy with a design composition of Fe-25Cr-20Ni-2Mo-0.35Y(2)O(3)-0.5Ti was fabricated by the process of mechanical alloying and the hot isostatic press. The ODS alloy shows very fine grains with an average size of 300 nm and homogeneously dispersed ultrafine Y2Ti2O7 particles with sizes between several nm to tens nm. The effects of plastic deformation combined with annealing on the tensile property were investigated. The treatments of forging, rolling and annealing can balance the strength and plasticity of the alloy effectively. The microstructure and the mechanical property of the Mo alloyed ODS austenitic alloy were compared with a similar ODS austenitic steel without Mo. The addition of Mo shows almost no influence on the microstructure, while can improve the tensile strength obviously, especially at the high temperature of 700 degrees C.
引用
收藏
页码:175 / 182
页数:8
相关论文
共 25 条
[1]  
[Anonymous], 2003, E101903 ASTM INT
[2]   Hydrogen susceptibility of nano-sized oxide dispersed austenitic steel for fusion reactor [J].
Baek, Seung-Wook ;
Song, Eun Ju ;
Kim, Jung Hyun ;
Lee, Yun-Hee ;
Ryu, Kwon Sang ;
Kim, Sa-Woong .
FUSION ENGINEERING AND DESIGN, 2017, 121 :105-110
[3]   Production, microstructure and mechanical properties of two different austenitic ODS steels [J].
Graening, T. ;
Rieth, M. ;
Hoffmann, J. ;
Moeslang, A. .
JOURNAL OF NUCLEAR MATERIALS, 2017, 487 :348-361
[4]   Recent developments in stainless steels [J].
Lo, K. H. ;
Shek, C. H. ;
Lai, J. K. L. .
MATERIALS SCIENCE & ENGINEERING R-REPORTS, 2009, 65 (4-6) :39-104
[5]   Effect of hot cross rolling on the microstructure and mechanical properties of an Fe-14Cr ODS ferritic steel [J].
Macias-Delgado, J. ;
Leguey, T. ;
de Castro, V. .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2018, 711 :448-459
[6]   Microstructure and Mechanical Properties of Ultrafine-Grained Austenitic Oxide Dispersion Strengthened Steel [J].
Mao, Xiaodong ;
Kang, Suk Hoon ;
Kim, Tae Kyu ;
Kim, Seul Cham ;
Oh, Kyu Hwan ;
Jang, Jinsung .
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2016, 47A (11) :5334-5343
[7]   Atomistic investigations of κ-carbide precipitation in austenitic Fe-Mn-Al-C lightweight steels and the effect of Mo addition [J].
Moon, Joonoh ;
Park, Seong-Jun ;
Jang, Jae Hoon ;
Lee, Tae-Ho ;
Lee, Chang-Hoon ;
Hong, Hyun-Uk ;
Suh, Dong-Woo ;
Kim, Seong Hoon ;
Han, Heung Nam ;
Lee, Bong Ho .
SCRIPTA MATERIALIA, 2017, 127 :97-101
[8]   Structural materials for Gen-IV nuclear reactors: Challenges and opportunities [J].
Murty, K. L. ;
Charit, I. .
JOURNAL OF NUCLEAR MATERIALS, 2008, 383 (1-2) :189-195
[9]   Recent developments in irradiation-resistant steels [J].
Odette, G. R. ;
Alinger, M. J. ;
Wirth, B. D. .
ANNUAL REVIEW OF MATERIALS RESEARCH, 2008, 38 (471-503) :471-503
[10]   In situ observation, of damage structure in ODS austenitic steel during electron irradiation [J].
Oka, H. ;
Watanabe, M. ;
Kinoshita, H. ;
Shibayama, T. ;
Hashimoto, N. ;
Ohnuki, S. ;
Yamashita, S. ;
Ohtsuka, S. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :279-282