Microstructural Modifications due to Tungsten and Tantalum in 9Cr Reduced Activation Ferritic Martensitic Steels on Creep Exposure

被引:15
作者
Mythili, R. [1 ]
Ravikirana [2 ]
Vanaja, J. [1 ]
Laha, K. [1 ]
Saroja, S. [1 ]
Jayakumar, T. [1 ]
Mathew, M. D. [1 ]
Rajendrakumar, E. [3 ]
机构
[1] Indira Gandhi Ctr Atom Res, Met & Mat Grp, Kalpakkam 603102, Tamil Nadu, India
[2] Indira Gandhi Ctr Atom Res, Homi Bhabha Natl Inst, Kalpakkam 603102, Tamil Nadu, India
[3] Inst Plasma Res, Gandhinagar 382428, India
来源
6TH INTERNATIONAL CONFERENCE ON CREEP, FATIGUE AND CREEP-FATIGUE INTERACTION | 2013年 / 55卷
关键词
Reduced activation ferritic/martensitic steel; thermal aging; creep; microstructure; FERRITIC/MARTENSITIC STEELS; REACTORS;
D O I
10.1016/j.proeng.2013.03.257
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Replacement of Mo and Nb by W and Ta in modified 9Cr-1Mo class of steels has been significantly useful for achieving reduced activity and improved mechanical properties. The addition of W and Ta strongly influences microstructure which comprises of the substructural changes and precipitation kinetics under both thermal and stress exposure. This study focusses on the effect of W and Ta on microstructural changes on thermal and creep exposure at 823K in 9Cr-W-Ta-0.2V-0.1C steels, with W and Ta concentrations varying from 1 to 2% and 0.06 to 0.14% respectively. Increase in W from 1 to 1.4 or 2%, was beneficial to retain lath structure and retard the coarsening of M23C6 during long term thermal aging. Detailed microstructural investigation of the steesl after creep deformation showed extensive subgrain formation and coarsening of M23C6 carbides than just thermal exposure. Influence of W on subgrain size was more pronounced than Ta. Increase in W was found to be useful to control the coarsening rate of M23C6 carbides, even under stress, while MX precipitate size showed no significant change. (C) 2013 The Authors. Published by Elsevier Ltd.
引用
收藏
页码:295 / 299
页数:5
相关论文
共 7 条
[1]   On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors [J].
Baluc, N ;
Schäublin, R ;
Spätig, P ;
Victoria, M .
NUCLEAR FUSION, 2004, 44 (01) :56-61
[2]  
Butterworth G.L., 1991, J NUCL MATER, V135, P179
[3]   Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors [J].
Klueh, RL .
INTERNATIONAL MATERIALS REVIEWS, 2005, 50 (05) :287-310
[4]   Recent progress toward development of reduced activation ferritic/martensitic steels for fusion structural applications [J].
Kurtz, R. J. ;
Alamo, A. ;
Lucon, E. ;
Huang, Q. ;
Jitsukawa, S. ;
Kimura, A. ;
Klueh, R. L. ;
Odette, G. R. ;
Petersen, C. ;
Sokolov, M. A. ;
Spaetig, P. ;
Rensman, J. -W. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :411-417
[5]  
Sakasegawa H., 2002, FUSION ENGG DESIGN, V671, P61
[6]  
Sakasegawa H., 2002, J NUCL MATER, V490, P307
[7]   Effect of W on recovery of lath structure during creep of high chromium martensitic steels [J].
Sawada, K ;
Takeda, M ;
Maruyama, K ;
Ishii, R ;
Yamada, M ;
Nagae, Y ;
Komine, R .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 1999, 267 (01) :19-25