Grain boundary character dependence of radiation-induced segregation in a model Ni-Cr alloy

被引:34
作者
Barr, Christopher M. [1 ]
Barnard, Leland [2 ]
Nathaniel, James E. [1 ]
Hattar, Khalid [3 ]
Unocic, Kinga A. [4 ]
Szlufarska, Izabela [2 ,5 ]
Morgan, Dane [2 ,5 ]
Taheri, Mitra L. [1 ]
机构
[1] Drexel Univ, Dept Mat Sci & Engn, Philadelphia, PA 19104 USA
[2] Univ Wisconsin, Dept Mat Sci & Engn, Madison, WI 53706 USA
[3] Sandia Natl Labs, Radiat Solid Interact Grp, Albuquerque, NM 87185 USA
[4] Oak Ridge Natl Lab, Div Mat Sci & Technol, Oak Ridge, TN 37831 USA
[5] Univ Wisconsin, Mat Sci Program, Madison, WI 53706 USA
基金
美国能源部; 美国国家科学基金会;
关键词
AUSTENITIC STAINLESS-STEEL; INDUCED SOLUTE SEGREGATION; TWIN BOUNDARIES; FERRITIC/MARTENSITIC STEEL; IN-SITU; IRRADIATION; METALS; DAMAGE; MISORIENTATION; SIMULATION;
D O I
10.1557/jmr.2015.34
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Ni-based fcc alloys are frequently used as critical structural materials in nuclear energy applications. Despite extensive studies, fundamental questions remain regarding point defect migration and solute segregation as a function of grain boundary character after irradiation. In this study, a coupled experimental and modeling approach is used to understand the response of grain boundary character in a model Ni-5Cr alloy after high temperature heavy-ion irradiation. Radiation-induced segregation and void denuded zones were experimentally examined as a function of grain boundary character, while a kinetic rate theory model with grain boundary character boundary conditions was used to theoretically model Cr depletion in the alloy system. The results highlight major variations in the radiation response between the coherent and incoherent twin grain boundaries, but show limited disparity in defect sink strength between random low- and high-angle grain boundary regimes.
引用
收藏
页码:1290 / 1299
页数:10
相关论文
共 49 条
[1]   Modeling radiation-induced segregation in austenitic Fe-Cr-Ni alloys [J].
Allen, TR ;
Was, GS .
ACTA MATERIALIA, 1998, 46 (10) :3679-3691
[2]   Role of atomic structure on grain boundary-defect interactions in Cu [J].
Bai, Xian-Ming ;
Vernon, Louis J. ;
Hoagland, Richard G. ;
Voter, Arthur F. ;
Nastasi, Michael ;
Uberuaga, Blas Pedro .
PHYSICAL REVIEW B, 2012, 85 (21)
[3]   Efficient Annealing of Radiation Damage Near Grain Boundaries via Interstitial Emission [J].
Bai, Xian-Ming ;
Voter, Arthur F. ;
Hoagland, Richard G. ;
Nastasi, Michael ;
Uberuaga, Blas P. .
SCIENCE, 2010, 327 (5973) :1631-1634
[4]   Ab initio molecular dynamics simulation of interstitial diffusion in Ni-Cr alloys and implications for radiation induced segregation [J].
Barnard, L. ;
Morgan, D. .
JOURNAL OF NUCLEAR MATERIALS, 2014, 449 (1-3) :225-233
[5]   Modeling radiation induced segregation in Ni-Cr model alloys from first principles [J].
Barnard, L. ;
Tucker, J. D. ;
Choudhury, S. ;
Allen, T. R. ;
Morgan, D. .
JOURNAL OF NUCLEAR MATERIALS, 2012, 425 (1-3) :8-15
[6]   Anisotropic radiation-induced segregation in 316L austenitic stainless steel with grain boundary character [J].
Barr, Christopher M. ;
Vetterick, Gregory A. ;
Unocic, Kinga A. ;
Hattar, Khalid ;
Bai, Xian-Ming ;
Taheri, Mitra L. .
ACTA MATERIALIA, 2014, 67 :145-155
[7]  
Basu B.K., 1965, Acta Metall, V13, P1117
[8]   STRUCTURE OF HIGH-ANGLE GRAIN BOUNDARIES [J].
BRANDON, DG .
ACTA METALLURGICA, 1966, 14 (11) :1479-&
[9]   Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals [J].
Bruemmer, SM ;
Simonen, EP ;
Scott, PM ;
Andresen, PL ;
Was, GS ;
Nelson, JL .
JOURNAL OF NUCLEAR MATERIALS, 1999, 274 (03) :299-314
[10]   DISLOCATION LOOP-FREE ZONES AROUND GRAIN-BOUNDARIES IN QUENCHED ALUMINUM AND ALUMINUM-ALLOYS [J].
BURKE, J ;
STUCKEY, D .
PHILOSOPHICAL MAGAZINE, 1975, 31 (05) :1063-1080