Dislocation loop evolution during in-situ ion FeCrAl alloys

被引:100
作者
Haley, Jack C. [1 ]
Briggs, Samuel A. [2 ]
Edmondson, Philip D. [3 ]
Sridharan, Kumar [2 ]
Roberts, Steve G. [1 ]
Lozano-Perez, Sergio
Field, Kevin G. [3 ]
机构
[1] Univ Oxford, Oxford OX1 3PH, England
[2] Univ Wisconsin, Madison, WI 53706 USA
[3] Oak Ridge Natl Lab, 1 Bethel Valley Rd, Oak Ridge, TN 37831 USA
基金
英国工程与自然科学研究理事会;
关键词
FeCrAl; Dislocation loops; Radiation damage; In-situ; Accident tolerant; TRANSMISSION ELECTRON-MICROSCOPY; HIGH-TEMPERATURE OXIDATION; FE-CR ALLOYS; TEM CHARACTERIZATION; DAMAGE EVOLUTION; RADIATION-DAMAGE; THIN-FOILS; NEUTRON; IRRADIATION; IRON;
D O I
10.1016/j.actamat.2017.07.011
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Model FeCrAl alloys of Fe-10%Cr-5%Al, Fe-12%Cr-4.5%Al, Fe-15%Cr-4%Al, and Fe-18%Cr-3%Al (in wt %) were irradiated with 1 MeV Kr++ ions in-situ with transmission electron microscopy to a dose of 2.5 displacements per atom (dpa) at 320 degrees C. In all cases, the microstructural damage consisted of dislocation loops with 1/2 < 111 > and < 100 > Burgers vectors. The proportion of 1/2 < 111 > dislocation loops varied from similar to 50% in the Fe-10%Cr-5%Al model alloy and the Fe-18Cr%-3%Al model alloy to a peak of similar to 80% in the model Fe-15%Cr-4.5%Al alloy. The dislocation loop volume density increased with dose for all alloys and showed signs of approaching an upper limit. The total loop populations at 2.5 dpa had a slight (and possibly insignificant) decline as the chromium content was increased from 10 to 15 wt %, but the Fe-18%Cr-3%Al alloy had a dislocation loop population similar to 50% smaller than the other model alloys. The largest dislocation loops in each alloy had image sizes of close to 20 nm in the micrographs, and the median diameters for all alloys ranged from 6 to 8 nm. Nature analysis by the inside-outside method indicated most dislocation loops were interstitial type. (C) 2017 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.
引用
收藏
页码:390 / 401
页数:12
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