Radiation-induced segregation on defect clusters in single-phase concentrated solid-solution alloys

被引:256
作者
Lu, Chenyang [1 ]
Yang, Taini [1 ]
Jin, Ke [2 ]
Gao, Ning [3 ]
Xiu, Pengyuan [1 ]
Zhang, Yanwen [2 ,4 ]
Gao, Fei [1 ]
Bei, Hongbin [2 ]
Weber, William J. [2 ,4 ]
Sun, Kai [5 ]
Dong, Yan [5 ]
Wang, Lumin [1 ,5 ]
机构
[1] Univ Michigan, Dept Nucl Engn & Radiol Sci, Ann Arbor, MI 48109 USA
[2] Oak Ridge Natl Lab, Mat Sci & Technol Div, Oak Ridge, TN 37831 USA
[3] Chinese Acad Sci, Inst Modem Phys, Lan Zhou 73000, Gansu, Peoples R China
[4] Univ Tennessee, Dept Mat Sci & Engn, Knoxville, TN 37996 USA
[5] Univ Michigan, Dept Mat Sci & Engn, Ann Arbor, MI 48109 USA
关键词
Radiation induced segregation; Single-phase concentrated solid -solution alloys; High-entropy alloys; Electron energy loss spectroscopy; Molecular static simulations; HIGH-ENTROPY ALLOY; IRRADIATION; EVOLUTION; STABILITY; FEATURES; NI;
D O I
10.1016/j.actamat.2017.01.019
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
A group of single-phase concentrated solid-solution alloys (SP-CSAs), including NiFe, NiCoFe, NiCoFeCr, as well as a high entropy alloy NiCoFeCrMn, was irradiated with 3 MeV Ni2+ ions at 773 K to a fluence of 5 x 10(16) ions/cm(2) for the study of radiation response with increasing compositional complexity. Advanced transmission electron microscopy (TEM) with electron energy loss spectroscopy (EELS) was used to characterize the dislocation loop distribution and radiation-induced segregation (RIS) on defect clusters in the SP-CSAs. The results show that a higher fraction of faulted loops exists in the more compositionally complex alloys, which indicate that increasing compositional complexity can extend the incubation period and delay loop growth. The RIS behaviors of each element in the SP-CSAs were observed as follows: Ni and Co tend to enrich, but Cr, Fe and Mn prefer to deplete near the defect clusters. RIS level can be significantly suppressed by increasing compositional complexity due to the sluggish atom diffusion. According to molecular static (MS) simulations, "disk" like segregations may form near the faulted dislocation loops in the SP-CSAs. Segregated elements tend to distribute around the whole faulted loop as a disk rather than only around the edge of the loop. (C) 2017 Acta Materialia Inc. Published by Elsevier Ltd. This is an open access article under the CC BY-NC-ND license
引用
收藏
页码:98 / 107
页数:10
相关论文
共 25 条
[1]   Point defect evolution in Ni, NiFe and NiCr alloys from atomistic simulations and irradiation experiments [J].
Aidhy, Dilpuneet S. ;
Lu, Chenyang ;
Jin, Ke ;
Bei, Hongbin ;
Zhang, Yanwen ;
Wang, Lumin ;
Weber, William J. .
ACTA MATERIALIA, 2015, 99 :69-76
[2]   Swelling and radiation-induced segregation in austentic alloys [J].
Allen, TR ;
Cole, JI ;
Gan, J ;
Was, GS ;
Dropek, R ;
Kenik, EA .
JOURNAL OF NUCLEAR MATERIALS, 2005, 342 (1-3) :90-100
[3]  
[Anonymous], CRACK INITIATION MEC
[4]   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
[5]   Interatomic potential for studying ageing under irradiation in stainless steels: the FeNiCr model alloy [J].
Bonny, G. ;
Castin, N. ;
Terentyev, D. .
MODELLING AND SIMULATION IN MATERIALS SCIENCE AND ENGINEERING, 2013, 21 (08)
[6]   Interatomic potential to study plasticity in stainless steels: the FeNiCr model alloy [J].
Bonny, G. ;
Terentyev, D. ;
Pasianot, R. C. ;
Ponce, S. ;
Bakaev, A. .
MODELLING AND SIMULATION IN MATERIALS SCIENCE AND ENGINEERING, 2011, 19 (08)
[7]   Microchemical and microstructural evolution of AISI 304 stainless steel irradiated in EBR-II at PWR-relevant dpa rates [J].
Dong, Y. ;
Sencer, B. H. ;
Garner, F. A. ;
Marquis, E. A. .
JOURNAL OF NUCLEAR MATERIALS, 2015, 467 :692-702
[8]   A fracture-resistant high-entropy alloy for cryogenic applications [J].
Gludovatz, Bernd ;
Hohenwarter, Anton ;
Catoor, Dhiraj ;
Chang, Edwin H. ;
George, Easo P. ;
Ritchie, Robert O. .
SCIENCE, 2014, 345 (6201) :1153-1158
[9]   Mechanism of Radiation Damage Reduction in Equiatomic Multicomponent Single Phase Alloys [J].
Granberg, F. ;
Nordlund, K. ;
Ullah, Mohammad W. ;
Jin, K. ;
Lu, C. ;
Bei, H. ;
Wang, L. M. ;
Djurabekova, F. ;
Weber, W. J. ;
Zhang, Y. .
PHYSICAL REVIEW LETTERS, 2016, 116 (13)
[10]  
Jenkins M.L., 2000, CHARACTERISATION RAD