Analytical characterisation of oxide dispersion strengthened steels for fusion reactors

被引:19
作者
de Castro, V. [1 ,2 ]
Lozano-Perez, S. [2 ]
Marquis, E. A. [2 ,3 ]
Auger, M. A. [1 ]
Leguey, T. [1 ]
Pareja, R. [1 ]
机构
[1] Univ Carlos III Madrid, Dept Fis, Leganes 28911, Spain
[2] Univ Oxford, Dept Mat, Oxford OX1 3PH, England
[3] Univ Michigan, Dept Mat Sci & Engn, Ann Arbor, MI 48109 USA
基金
英国工程与自然科学研究理事会;
关键词
ODS steel; Nanoparticles; Transmission electron microscopy; Atom probe tomography; ODS-EUROFER; BREEDING BLANKET; IRRADIATION; PARTICLES; BEHAVIOR; EELS;
D O I
10.1179/1743284710Y.0000000013
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Reduced activation ferritic/martensitic and ferritic steels strengthened by a dispersion of oxide nanoparticles have been considered viable structural materials for fusion applications above 550 degrees C. However, the microstructural stability and mechanical behaviour of these steels subjected to the aggressive operating conditions of these reactors are not well known. An accelerated development of these materials is crucial if they are going to be used in future power reactors. Then, it is indispensable to understand their atomic scale evolution under high temperature and irradiation conditions. The present paper reviews how the combination of transmission electron microscopy and atom probe tomography has been successfully applied for the characterisation of these steels at the near atomic scale, to reveal the nanoparticle structure, grain boundary chemistry and void distribution.
引用
收藏
页码:719 / 723
页数:5
相关论文
共 26 条
[1]   Microstructural changes of neutron irradiated ODS ferritic and martensitic steels [J].
Akasaka, N ;
Yamashita, S ;
Yoshitake, T ;
Ukai, S ;
Kimura, A .
JOURNAL OF NUCLEAR MATERIALS, 2004, 329 :1053-1056
[2]  
AUGER MA, J NUCL MAT IN PRESS
[3]   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
[4]   Mechanical and microstructural behaviour of Y2O3ODS EUROFER 97 [J].
de Castro, V. ;
Leguey, T. ;
Munoz, A. ;
Monge, M. A. ;
Fernandez, P. ;
Lancha, A. M. ;
Pareja, R. .
JOURNAL OF NUCLEAR MATERIALS, 2007, 367 (SPEC. ISS.) :196-201
[5]   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
[6]  
DECASTRO V, J NUCL MAT IN PRESS
[7]   Status of the European breeding blanket technology [J].
Giancarli, L ;
DalleDonne, M ;
Dietz, W .
FUSION ENGINEERING AND DESIGN, 1997, 36 (01) :57-74
[8]  
Jenkins ML, 2001, S MICRO MAT SCI, P1
[9]   Thermal helium desorption behavior in advanced ferritic steels [J].
Kimura, A ;
Sugano, R ;
Matsushita, Y ;
Ukai, S .
JOURNAL OF PHYSICS AND CHEMISTRY OF SOLIDS, 2005, 66 (2-4) :504-508
[10]   New insights into the structure of ODS particles in the ODS-Eurofer alloy [J].
Klimenkov, M. ;
Lindau, R. ;
Moeslang, A. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 386-88 :553-556