Mechanism of dislocation channel-induced irradiation assisted stress corrosion crack initiation in austenitic stainless steel

被引:65
作者
McMurtrey, M. D. [1 ]
Cui, B. [2 ]
Robertson, I. [2 ,3 ]
Farkas, D. [4 ]
Was, G. S. [1 ]
机构
[1] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA
[2] Univ Illinois, Dept Mat Sci & Engn, Urbana, IL 61801 USA
[3] Univ Wisconsin, Dept Mat Sci & Engn, Madison, WI 53706 USA
[4] Virginia Tech, Dept Mat Sci & Engn, Blacksburg, VA 24061 USA
关键词
Irradiation assisted stress corrosion cracking; Dislocation channels; Intergranular cracking; Discontinuous slip; Grain boundaries; GRAIN-BOUNDARIES; LOCALIZED DEFORMATION; ALLOYS; SEGREGATION; COPPER; DAMAGE; IASCC; WATER;
D O I
10.1016/j.cossms.2015.04.001
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The mechanism by which dislocation channeling induces irradiation assisted stress corrosion cracking was determined using Fe-13Cr15Ni austenitic stainless steel irradiated with protons to a dose of 5 dpa and strained at high temperature in both argon and simulated boiling water reactor normal water chemistry environments. Straining induced dislocation channels that were characterized by digital image correlation and confocal microscopy. Dislocation channels were found to be either continuous across the boundary, discontinuous, or discontinuous with slip in the boundary. Discontinuous channels were found to contain the least amount of strain but have the highest propensity for initiating cracks. Discontinuous dislocation channel-grain boundary intersections were shown to have the highest local stress. TEM in-situ straining of irradiated steels and atomistic simulation of dislocation-grain boundary interaction provided supporting evidence that channels that were unable to transfer strain underwent cracking. The inability of channels to relieve stress, by either slip in the adjacent grain or in the grain boundary, resulted in high local stresses and increased susceptibility to stress corrosion cracking initiation. (C) 2015 Elsevier Ltd. All rights reserved.
引用
收藏
页码:305 / 314
页数:10
相关论文
共 36 条
[1]  
a West E., 2011, Metall. Mater. Trans. A, V43, P136
[2]  
Alexandreanu B., 2002, THESIS U MICHIGAN AN
[3]   FUNDAMENTAL MODELING OF ENVIRONMENTAL CRACKING FOR IMPROVED DESIGN AND LIFETIME EVALUATION IN BWRS [J].
ANDERSEN, PL ;
FORD, FP .
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1994, 59 (1-3) :61-70
[4]   LIFE PREDICTION BY MECHANISTIC MODELING AND SYSTEM MONITORING OF ENVIRONMENTAL CRACKING OF IRON AND NICKEL-ALLOYS IN AQUEOUS SYSTEMS [J].
ANDRESEN, PL ;
FORD, FP .
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 1988, 103 (01) :167-184
[5]   Effect of ion irradiation-produced defects on the mobility of dislocations in 304 stainless steel [J].
Briceno, M. ;
Fenske, J. ;
Dadfarnia, M. ;
Sofronis, P. ;
Robertson, I. M. .
JOURNAL OF NUCLEAR MATERIALS, 2011, 409 (01) :18-26
[6]   Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels [J].
Busby, JT ;
Was, GS ;
Kenik, EA .
JOURNAL OF NUCLEAR MATERIALS, 2002, 302 (01) :20-40
[7]   Influence of irradiation damage on slip transfer across grain boundaries [J].
Cui, B. ;
Kacher, J. ;
McMurtrey, M. ;
Was, G. ;
Robertson, I. M. .
ACTA MATERIALIA, 2014, 65 :150-160
[8]   Micromechanistic origin of irradiation-assisted stress corrosion cracking [J].
Cui, Bai ;
McMurtrey, Michael D. ;
Was, Gary S. ;
Robertson, Ian M. .
PHILOSOPHICAL MAGAZINE, 2014, 94 (36) :4197-4218
[9]   Initiation and propagation of cleared channels in neutron-irradiated pure copper and a precipitation hardened CuCrZr alloy [J].
Edwards, DJ ;
Singh, BN ;
Bilde-Sorensen, JB .
JOURNAL OF NUCLEAR MATERIALS, 2005, 342 (1-3) :164-178
[10]   Modelling of the effect of dislocation channel on intergranular microcrack nucleation in pre-irradiated austenitic stainless steels during low strain rate tensile loading [J].
Evrard, Pierre ;
Sauzay, Maxime .
JOURNAL OF NUCLEAR MATERIALS, 2010, 405 (02) :83-94