Tensile and fracture characteristics of oxide dispersion strengthened Fe-12Cr produced by hot isostatic pressing

被引：7
作者：
de Castro, Vanessa [1 ]
Maria Garces-Usan, Jose [1 ]
Leguey, Teresa [1 ]
Pareja, Ramiro [1 ]
机构：
[1] Univ Carlos III Madrid, Dept Fis, Madrid 28911, Spain
来源：
JOURNAL OF NUCLEAR MATERIALS | 2013年 / 442卷 / 1-3期
关键词：
FERRITIC/MARTENSITIC STEELS; STRUCTURAL-MATERIALS; SECONDARY PHASES; FUSION-REACTORS; ALLOYS;
D O I：
10.1016/j.jnucmat.2012.12.034
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The mechanical characteristics of a model oxide dispersion strengthened (ODS) alloy with nominal composition Fe-12 wt% Cr-0.4 wt%Y2O3 were investigated by means of microhardness measurements, tensile tests up to fracture in the temperature range of 298-973 K, and fracture surface analyses. A non-ODS Fe-12 wt%Cr alloy was also studied to assess the real capacity of the oxide dispersion for strengthening the alloy. The materials were produced by mechanical alloying followed by hot isostatic pressing consolidation and heat treatment at 1023 K. The strengthening effect of the oxide nanodispersion was effective at all temperatures studied, although the tensile strength converges towards the one obtained for the reference alloy at higher temperatures. Moreover, the ODS alloys failed prematurely at T < 673 K due to the presence of Y-rich inclusions, as seen in the fracture surface of these alloys. (C) 2013 Elsevier B. V. All rights reserved.
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收藏
页码：S119 / S123
页数：5
相关论文
共 15 条
[1]  
[Anonymous], 2001, HIGH CHROMIUM FERRIT
[2]   Microstructure and mechanical properties of ultrafine-grained Fe-14Cr and ODS Fe-14Cr model alloys [J].
Auger, M. A. ;
Leguey, T. ;
Munoz, A. ;
Monge, M. A. ;
de Castro, V. ;
Fernandez, P. ;
Garces, G. ;
Pareja, R. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :213-216
[3]   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
[4]   Fissile core and Tritium-Breeding Blanket: structural materials and their requirements [J].
Boutard, Jean-Louis ;
Alamo, Ana ;
Lindau, Rainer ;
Rieth, Michael .
COMPTES RENDUS PHYSIQUE, 2008, 9 (3-4) :287-302
[5]   Analytical characterization of secondary phases and void distributions in an ultrafine-grained ODS Fe-14Cr model alloy [J].
de Castro, V. ;
Leguey, T. ;
Auger, M. A. ;
Lozano-Perez, S. ;
Jenkins, M. L. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) :217-220
[6]   Stability of nanoscale secondary phases in an oxide dispersion strengthened Fe-12Cr alloy [J].
de Castro, V. ;
Marquis, E. A. ;
Lozano-Perez, S. ;
Pareja, R. ;
Jenkins, M. L. .
ACTA MATERIALIA, 2011, 59 (10) :3927-3936
[7]   Analytical characterisation of oxide dispersion strengthened steels for fusion reactors [J].
de Castro, V. ;
Lozano-Perez, S. ;
Marquis, E. A. ;
Auger, M. A. ;
Leguey, T. ;
Pareja, R. .
MATERIALS SCIENCE AND TECHNOLOGY, 2011, 27 (04) :719-723
[8]   Microstructural characterization of Y2O3 ODS-Fe-Cr model alloys [J].
de Castro, V. ;
Leguey, T. ;
Munoz, A. ;
Monge, M. A. ;
Pareja, R. ;
Marquis, E. A. ;
Lozano-Perez, S. ;
Jenkins, M. L. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :449-452
[9]   Oxide dispersion-strengthened steels: A comparison of some commercial and experimental alloys [J].
Klueh, RL ;
Shingledecker, JP ;
Swindeman, RW ;
Hoelzer, DT .
JOURNAL OF NUCLEAR MATERIALS, 2005, 341 (2-3) :103-114
[10]   Mechanical and microstructural properties of a hipped RAFM ODS-steel [J].
Lindau, R ;
Möslang, A ;
Schirra, M ;
Schlossmacher, P ;
Klimenkov, M .
JOURNAL OF NUCLEAR MATERIALS, 2002, 307 (1 SUPPL.) :769-772
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