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
[21]   Effects of grain boundary misorientation on radiation-induced solute segregation in proton irradiated 304 stainless steels [J].
Kai, JJ ;
Chen, FR ;
Duh, TS .
MATERIALS TRANSACTIONS, 2004, 45 (01) :40-50
[22]   Radiation-induced degradation of stainless steel light water reactor internals [J].
Kenik, Edward A. ;
Busby, Jeremy T. .
MATERIALS SCIENCE & ENGINEERING R-REPORTS, 2012, 73 (7-8) :67-83
[23]   ON THE MECHANISMS OF POINT-DEFECT ABSORPTION BY GRAIN AND TWIN BOUNDARIES [J].
KING, AH ;
SMITH, DA .
PHILOSOPHICAL MAGAZINE A-PHYSICS OF CONDENSED MATTER STRUCTURE DEFECTS AND MECHANICAL PROPERTIES, 1980, 42 (04) :495-512
[24]   Observation and rate theory modeling of grain boundary segregation in Σ3 twin boundaries in ion-irradiated stainless steel 316 [J].
Lee, Gyeong-Geun ;
Jin, Hyung-Ha ;
Lee, Yong-Bok ;
Kwon, Junhyun .
JOURNAL OF NUCLEAR MATERIALS, 2014, 449 (1-3) :234-241
[25]   In situ probing of the evolution of irradiation-induced defects in copper [J].
Li, N. ;
Hattar, K. ;
Misra, A. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 439 (1-3) :185-191
[26]   Incoherent twin boundary migration induced by ion irradiation in Cu [J].
Li, N. ;
Wang, J. ;
Wang, Y. Q. ;
Serruys, Y. ;
Nastasi, M. ;
Misra, A. .
JOURNAL OF APPLIED PHYSICS, 2013, 113 (02)
[27]   Survey of computed grain boundary properties in face-centered cubic metals: I. Grain boundary energy [J].
Olmsted, David L. ;
Foiles, Stephen M. ;
Holm, Elizabeth A. .
ACTA MATERIALIA, 2009, 57 (13) :3694-3703
[28]  
Perks J. M., 1986, AERER12121
[29]  
Priester L., 2013, Grain Boundaries from Theory to Engineering
[30]   A methodology for grain boundary plane assessment by single-section trace analysis [J].
Randle, V .
SCRIPTA MATERIALIA, 2001, 44 (12) :2789-2794