Creep behavior of ODS materials: A study of dislocations/precipitates interactions

被引:45
作者
Malaplate, J. [1 ]
Mompiou, F. [2 ]
Bechade, J. -L.
Van den Berghe, T.
Ratti, M.
机构
[1] CEA Saclay, Dept Mat Nucl, DEN DANS DMN SRMA LA2M, F-91191 Gif Sur Yvette, France
[2] CNRS, Ctr Elaborat Mat & Etud Struct, F-31055 Toulouse 4, France
关键词
STRENGTHENED FERRITIC STEELS; ALLOY MA957; IRRADIATION; EQUATION; STRESS;
D O I
10.1016/j.jnucmat.2010.12.059
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Creep experiments performed at 650 degrees C and 250 MPa on MA957 and CEA-developed 18%Cr ferritic Oxide Dispersion Strengthened (ODS) steels emphasize the particular creep behavior of ODS alloys. To understand the influence of oxide particles, we focused on the dislocation microstructure and their interaction mechanisms with precipitates. Microstructural characterization were performed using Transmission Electron Microscopy (TEM) on both un-deformed alloys and on 650 degrees C-250 MPa creep tested MA957 samples. No noticeable differences were observed, and dislocations seem to be anchored by precipitate particles. The dynamic behavior was studied by in situ TEM straining experiments at room temperature on MA957. Observation of dislocation motions indicates that interactions with particles, including pinning, control the flow stress at least at room temperature. At 650 degrees C, other mechanism is probably predominant. (C) 2011 Elsevier B.V. All rights reserved.
引用
收藏
页码:205 / 208
页数:4
相关论文
共 16 条
[11]   Evaluation of threshold stress of the MA957 ODS ferrtic alloy [J].
Sakasegawa, H. ;
Chaffron, L. ;
Legendre, F. ;
Brocq, M. ;
Boulanger, L. ;
Poissonnet, S. ;
de Carlan, Y. ;
Bechade, J. ;
Cozzika, T. ;
Malaplate, J. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :511-514
[12]   Creep constitutive equation of dual phase 9Cr-ODS steel [J].
Sakasegawa, Hideo ;
Ukai, Shigeharu ;
Tamura, Manabu ;
Ohtsuka, Satoshi ;
Tanigawa, Hiroyasu ;
Ogiwara, Hiroyuki ;
Kohyama, Akira ;
Fujiwara, Masayuki .
JOURNAL OF NUCLEAR MATERIALS, 2008, 373 (1-3) :82-89
[13]   Microstructural development under irradiation in European ODS ferritic/martensitic steels [J].
Schäublin, R ;
Ramar, A ;
Baluc, N ;
de Castro, V ;
Monge, MA ;
Leguey, T ;
Schmid, N ;
Bonjour, C .
JOURNAL OF NUCLEAR MATERIALS, 2006, 351 (1-3) :247-260
[14]   Creep behavior of oxide dispersion strengthened 8Cr-2WVTa and 8Cr-1W steels [J].
Shinozuka, K. ;
Tamura, M. ;
Esaka, H. ;
Shiba, K. ;
Nakamura, K. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 384 (01) :1-5
[15]   Irradiation creep and swelling from 400 to 600°C of the oxide dispersion strengthened ferritic alloy MA957 [J].
Toloczko, MB ;
Gelles, DS ;
Garner, FA ;
Kurtz, RJ ;
Abe, K .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :352-355
[16]  
ZAKINE C, 1994, THESIS ECOLE CENTRAL