Towards a reliable nanohardness-dose correlation of ion-irradiated materials from nanoindentation tests: A case study in proton-irradiated vanadium

被引:10
作者
Chen, Shang [1 ]
Yuan, Jiuxi [1 ]
Wang, Shumin [2 ]
Mei, Luyao [1 ]
Yan, Jiaohui [1 ]
Li, Lei [1 ]
Zhang, Qiuhong [1 ]
Zhu, Zhixi [1 ]
Lv, Jin [1 ]
Xue, Yunfei [1 ]
Dou, Yankun [2 ]
Xiao, Xiazi [3 ]
Guo, Xun [1 ,4 ]
Jin, Ke [1 ,4 ]
机构
[1] Beijing Inst Technol, Sch Mat Sci & Engn, Beijing 100081, Peoples R China
[2] China Inst Atom Energy, Reactor Engn Technol Res Inst, Beijing 102413, Peoples R China
[3] Cent South Univ, Sch Civil Engn, Dept Mech, Changsha 410075, Peoples R China
[4] Beijing Inst Technol, Adv Res Inst Multidisciplinary Sci, Beijing 100081, Peoples R China
关键词
Irradiation hardening; Nanoindentation; Dislocation loop; CPFEM; MD; FE-CR ALLOYS; CRYSTAL PLASTICITY; IN-SITU; NANO-INDENTATION; DISLOCATION; STEELS; EVOLUTION; HARDNESS; DAMAGE; SIZE;
D O I
10.1016/j.ijplas.2023.103804
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Nanoindentation has been commonly used for evaluating the hardening effects of ion-irradiated materials. Nonetheless, establishing a reliable correlation between the hardness and irradiation dose is never trivial, due to not only the intrinsic analytical challenges of this technique, such as size effects, pile-up effects, etc., but also the fact that the irradiation dose is usually uneven inside the stress volume under the indenter, especially near the depth of dose peak. In the present work, the hardening in pure V irradiated with 1 MeV proton at various fluences is investigated by using nanoindentation tests, combined with the characterization of both irradiation defects and dislocations of the indented material. Under the cross-sectional indentation, we demonstrate that the nanohardness-dose correlation can be unified from the samples irradiated to different fluences and at different depths on each sample, as long as the lateral spanning of indenter is carefully considered. Crystal-plasticity finite-element-modeling simulation results can well describe the measured hardening-dose correlation, as well as the observed features on the change in strained fields and pile-up effects after irradiations. Moreover, the measured hardness is further corrected for the dose-dependent pile-up based on the surface profiling, and the indentation size effects based on surface indentation tests for deeper indentation depth, to reach a reliable connection between the hardening effects and the irradiation dose. Furthermore, microstructural characterization of the indented materials shows the pinning of dislocation by irradiation defects and the sweeping of those defects during dislocation migration. Molecular dynamics results suggest that the drag of loops by edge dislocations might cause the annihilation or aggregation of small loops, which could be responsible for the lower density but the larger size of irradiation loops in the strained region.
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页数:21
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共 69 条
[1]   Hardening of self ion implanted tungsten and tungsten 5-wt% rhenium [J].
Armstrong, D. E. J. ;
Yi, X. ;
Marquis, E. A. ;
Roberts, S. G. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 432 (1-3) :428-436
[2]   Modeling the evolution of crystallographic dislocation density in crystal plasticity [J].
Arsenlis, A ;
Parks, DM .
JOURNAL OF THE MECHANICS AND PHYSICS OF SOLIDS, 2002, 50 (09) :1979-2009
[3]   Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties [J].
Aydogan, E. ;
Weaver, J. S. ;
Carvajal-Nunez, U. ;
Schneider, M. M. ;
Gigax, J. G. ;
Krumwiede, D. L. ;
Hosemann, P. ;
Saleh, T. A. ;
Mara, N. A. ;
Hoelzer, D. T. ;
Hilton, B. ;
Maloy, S. A. .
ACTA MATERIALIA, 2019, 167 :181-196
[4]   Interaction of Ti and Cr atoms with point defects in bcc vanadium: A DFT study [J].
Boev, A. O. ;
Aksyonov, D. A. ;
Kartamyshev, A. I. ;
Maksimenko, V. N. ;
Nelasov, I. V. ;
Lipnitskii, A. G. .
JOURNAL OF NUCLEAR MATERIALS, 2017, 492 :14-21
[5]   Irradiation hardening behavior of polycrystalline metals after low temperature irradiation [J].
Byun, TS ;
Farrell, K .
JOURNAL OF NUCLEAR MATERIALS, 2004, 326 (2-3) :86-96
[6]   Deformation dynamics of a neutron-irradiated aluminum alloy: An in situ synchrotron tomography study [J].
Chai, H. W. ;
Fan, D. ;
Yuan, J. C. ;
Hu, L. ;
Xie, H. L. ;
Du, G. H. ;
Feng, Q. J. ;
Zhou, W. ;
Huang, J. Y. .
ACTA MATERIALIA, 2023, 243
[7]   Irradiation-induced swelling and hardening in HfNbTaTiZr refractory high-entropy alloy [J].
Chang, Stanley ;
Tseng, Ko-Kai ;
Yang, Tzu-Yi ;
Chao, Der-Sheng ;
Yeh, Jien-Wei ;
Liang, Jenq-Horng .
MATERIALS LETTERS, 2020, 272
[8]   Interatomic potentials of W-V and W-Mo binary systems for point defects studies [J].
Chen, Yangchun ;
Liao, Xichuan ;
Gao, Ning ;
Hu, Wangyu ;
Gao, Fei ;
Deng, Huiqiu .
JOURNAL OF NUCLEAR MATERIALS, 2020, 531
[9]   Improved irradiation resistance of Cr-Fe alloy for Cr-coated Zircaloy application in accident tolerant fuel [J].
Cui, L. J. ;
Du, Y. F. ;
Yang, H. L. ;
Jovellana, J. A. K. ;
Shi, Q. Q. ;
Kano, S. ;
Abe, H. .
SCRIPTA MATERIALIA, 2023, 229
[10]   Mechanical properties of neutron-irradiated single crystal tungsten W(100) studied by indentation and FEM modelling [J].
Dellis, Spilios ;
Xiao, Xiazi ;
Terentyev, Dmitry ;
Mergia, Konstantina ;
Krimpalis, Spyros ;
Bakaev, Alexander ;
Messoloras, Spyros .
JOURNAL OF NUCLEAR MATERIALS, 2021, 551