Structural and chemical matrix evolution following neutron irradiation in a MA957 oxide dispersion strengthened material

被引：27
作者：
Ribis, J. [1 ]
机构：
[1] CEA, DEN, DMN, SRMA, F-91191 Gif Sur Yvette, France
来源：
JOURNAL OF NUCLEAR MATERIALS | 2013年 / 434卷 / 1-3期
关键词：
ORIENTATION RELATIONSHIPS; ALLOYS; NANOCLUSTERS; ZIRCONIUM; STEELS; DAMAGE;
D O I：
10.1016/j.jnucmat.2012.11.038
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The MA957 alloy has been irradiated in the french Phenix reactor at 412 degrees C up to 50 dpa and at 430 degrees C up to 75 dpa. For both irradiation conditions, the evolution of the matrix after neutron irradiation has been investigated by transmission electron microscopy especially focusing on the creation of structural defect as the dislocation loops and on the chemical evolution of the matrix. Some loops have been investigated and are found to be < 100 >{100} interstitial type loops. Further, it is shown that the largest Ti-rich particles start to dissolve and release in the surrounding matrix their component elements. Those elements could segregate to the grain boundary. Both irradiation conditions systematically lead to the formation of alpha' nano-cluster and Cr depletion at grain boundary. (C) 2012 Elsevier B.V. All rights reserved.
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收藏
页码：178 / 188
页数：11
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