Microstructural development of a heavily neutron-irradiated ODS ferritic steel (MA957) at elevated temperature

被引:71
作者
Yamashita, S.
Akasaka, N.
Ukai, S.
Ohmiki, S.
机构
[1] Japan Atom Energy Agcy JAEA, Oarai Res & Dev Ctr, Oarai, Ibaraki 3111393, Japan
[2] Hokkaido Univ, Grad Sch Engn, Sapporo, Hokkaido 0608628, Japan
关键词
D O I
10.1016/j.jnucmat.2007.03.145
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Microstructural observation was performed on a neutron-irradiated oxide dispersion strengthened (ODS) ferritic steel with emphasis on oxide behavior, including phase stability under irradiation at elevated temperature (similar to 973 K). Transmission electron microscopy observation of the Y-Ti complex oxide particles showed they were fine (similar to 40 nm) whereas the Ti-oxide particles were relatively coarse (similar to 300 nm). Dispersion parameters of oxide particles, such as mean size and number density, changed due to irradiation. This implies recoil resolution of the oxide particles. When irradiated at 973 K, some Y-Ti complex oxides survived and interacted with the dislocation structures, which delayed the dislocation recovery and stabilized the elongated grain structure. It is considered that oxide particles could be effective pinning points of dislocations in motion under irradiation to a dose of similar to 100 dpa. (c) 2007 Elsevier B.V. All rights reserved.
引用
收藏
页码:202 / 207
页数:6
相关论文
共 13 条
[1]   Assessment of ODS-14%Cr ferritic alloy for high temperature applications [J].
Alamo, A ;
Lambard, V ;
Averty, X ;
Mathon, MH .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :333-337
[2]   MICROSTRUCTURAL EVOLUTION OF AN OXIDE DISPERSION STRENGTHENED STEEL UNDER CHARGED-PARTICLE IRRADIATION [J].
ASANO, K ;
KOHNO, Y ;
KOHYAMA, A ;
SUZUKI, T ;
KUSANAGI, H .
JOURNAL OF NUCLEAR MATERIALS, 1988, 155 :928-934
[3]   Behavior of an oxide dispersion strengthened ferritic steel irradiated in Phenix [J].
Dubuisson, P ;
Schill, R ;
Hugon, MP ;
Grislin, I ;
Séran, JL .
EFFECTS OF RADIATION ON MATERIALS: 18TH INTERNATIONAL SYMPOSIUM, 1999, 1325 :882-898
[4]   Microstructural examination of commercial ferritic alloys at 200 dpa [J].
Gelles, DS .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :293-298
[5]   FABRICATION AND MECHANICAL-PROPERTIES OF OXIDE DISPERSION STRENGTHENING FERRITIC ALLOY CANNING TUBES FOR FAST-REACTOR FUEL-PINS [J].
HUET, JJ ;
COHEUR, L ;
DEBREMAECKER, A ;
DEWILDE, L ;
GEDOPT, J ;
HENDRIX, W ;
VANDERMEULEN, W .
NUCLEAR TECHNOLOGY, 1985, 70 (02) :215-219
[6]  
Little EA., 1996, EFFECTS RAD MAT 17 I, V1270, P739, DOI DOI 10.1520/STP16505S
[7]   Nanometer scale precipitation in ferritic MA/ODS alloy MA957 [J].
Miller, MK ;
Hoelzer, DT ;
Kenik, EA ;
Russell, KF .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :338-341
[8]   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
[9]   Irradiation creep of various ferritic alloys irradiated at ∼400°C in the PFR and FFTF reactors [J].
Toloczko, MB ;
Garner, FA ;
Eiholzer, CR .
JOURNAL OF NUCLEAR MATERIALS, 1998, 258 :1163-1166
[10]   Development of 9Cr-ODS martensitic steel claddings for fuel pins by means of ferrite to austenite phase transformation [J].
Ukai, S ;
Mizuta, S ;
Fujiwara, M ;
Okuda, T ;
Kobayashi, T .
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2002, 39 (07) :778-788