Dislocation loop evolution under ion irradiation in austenitic stainless steels

被引:91
作者
Etienne, A. [1 ,2 ]
Hernandez-Mayoral, M. [3 ]
Genevois, C. [1 ,2 ]
Radiguet, B. [1 ,2 ]
Pareige, P. [1 ,2 ]
机构
[1] Univ St Etienne, Grp Phys Mat, F-76801 St Etienne, France
[2] INSA Rouen, UMR 6634, CNRS, F-76801 St Etienne, France
[3] CIEMAT, Div Mat, Madrid 28040, Spain
关键词
DISPLACEMENT CASCADES; MICROSTRUCTURE EVOLUTION; PROPERTY CORRELATION; FERRITIC ALLOYS; NEUTRON; TEMPERATURE; METALS; ENERGY; DAMAGE; DEFORMATION;
D O I
10.1016/j.jnucmat.2010.02.009
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
A solution annealed 304 and a cold worked 316 austenitic stainless steels were irradiated from 0.36 to 5 dpa at 350 degrees C using 160 key Fe ions. Irradiated microstructures were characterized by transmission electron microscopy (TEM). Observations after irradiation revealed the presence of a high number density of Frank loops. Size and number density of Frank loops have been measured. Results are in good agreement with those observed in the literature and show that ion irradiation is able to simulate dislocation loop microstructure obtained after neutron irradiation. Experimental results and data from literature were compared with predictions from the cluster dynamic model, MFVIC (Mean Field Vacancy and Interstitial Clustering). It is able to reproduce dislocation loop population for neutron irradiation. Effects of dose rate and temperature on the loop number density are simulated by the model. Calculations for ion irradiations show that simulation results are consistent with experimental observations. However, results also show the model limitations due to the lack of accurate parameters. (C) 2010 Elsevier B.V. All rights reserved.
引用
收藏
页码:56 / 63
页数:8
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