Atomistic investigation of the interaction between an edge dislocation and 1/2<111> interstitial dislocation loops in irradiated tungsten

被引:5
作者
Yu, Ping [1 ]
Liu, Guisen [1 ]
Shen, Yao [1 ]
机构
[1] Shanghai Jiao Tong Univ, Sch Mat Sci & Engn, State Key Lab Met Matrix Composites, Shanghai 200240, Peoples R China
基金
中国博士后科学基金; 中国国家自然科学基金;
关键词
Irradiation hardening; Loop-dislocation interaction; Atomistic simulation; Tungsten; MOLECULAR-DYNAMICS SIMULATIONS; IN-SITU TEM; NEUTRON-IRRADIATION; MICROSTRUCTURAL DEVELOPMENT; MECHANICAL-PROPERTIES; SCREW DISLOCATIONS; ALLOYS; TEMPERATURE; DEFORMATION; EVOLUTION;
D O I
10.1016/j.ijplas.2024.104030
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
By impeding dislocation motion, the irradiation-induced dislocation loops cause irradiation hardening and further embrittlement of plasma-facing tungsten in fusion reactors, leading to its performance degradation. But fundamental questions regarding the mechanisms remain to be clarified and predictive model for loop hardening remains to be built. In this paper, interactions between gliding edge dislocations and interstitial dislocation loops (with Burger vector b(L) = 1/2 <111>) are studied using atomistic simulations. The influences of b(L) orientations, dislocation-loop intersection positions, loop sizes, and loading conditions (temperature and strain rate) on the interactions are systematically calculated and analyzed. Results show a large variety of interaction mechanisms, depending mainly on the relative orientations of b(L) to dislocation slip plane, while slightly affected by loading conditions. Although loops with b(L) parallel to the plane can be easily swept away by gliding dislocations, loops with b(L) inclined to dislocation slip plane can strongly pin the gliding dislocation by forming a sessile < 100 > segment, which would bend the dislocation line into a screw dipole. Thus, high stress is required for the dislocation line to break away from the inclined loops by cross-slip of each individual arm of the screw dipole coupled with glide of the < 100 > segment. On the other hand, increasing temperature and/or decreasing strain rate hardly change the above mechanisms, but monotonically reduce the obstruction by these loops. Simplifying the complex motion of the edge dislocation pinned by the inclined loops as a thermally-activated process of a 1/2[111] edge dislocation overcoming barriers, a hardening model for the inclined loops is proposed. This model well describes the dependence of loop strength on loop sizes, temperatures and strain rates. The model is then applied to predict irradiation hardening at experimental strain rates, and it shows reasonable agreement with experimental results.
引用
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页数:17
相关论文
共 69 条
[1]  
Anderson P. M., 2017, Theory of Dislocations
[2]  
[Anonymous], 2003, PERG MAT SER
[3]  
Argon A., 2007, Strengthening Mechanisms in Crystal Plasticity, V1st
[4]   A dislocation dynamics study of the transition from homogeneous to heterogeneous deformation in irradiated body-centered cubic iron [J].
Arsenlis, A. ;
Rhee, M. ;
Hommes, G. ;
Cook, R. ;
Marian, J. .
ACTA MATERIALIA, 2012, 60 (09) :3748-3757
[5]   EFFECT OF DISLOCATION SELF-INTERACTION ON OROWAN STRESS [J].
BACON, DJ ;
KOCKS, UF ;
SCATTERGOOD, RO .
PHILOSOPHICAL MAGAZINE, 1973, 28 (06) :1241-1263
[6]   Influence of kinetic effect on interaction between edge dislocation and irradiated dislocation loops in BCC Tantalum [J].
Bao, Qifan ;
Li, Zhenhuan ;
Zhu, Bida ;
Liang, Shuang ;
Zhu, Jianchang ;
Huang, Minsheng ;
Zhao, Lv ;
Zhu, Yaxin .
INTERNATIONAL JOURNAL OF PLASTICITY, 2023, 165
[7]   Assessment of hardening due to non-coherent precipitates in tungsten-rhenium alloys at the atomic scale [J].
Bonny, G. ;
Bakaev, A. ;
Terentyev, D. .
SCIENTIFIC REPORTS, 2019, 9 (1)
[8]   The relationship between hardness and yield stress in irradiated austenitic and ferritic steels [J].
Busby, JT ;
Hash, MC ;
Was, GS .
JOURNAL OF NUCLEAR MATERIALS, 2005, 336 (2-3) :267-278
[9]   Towards a reliable nanohardness-dose correlation of ion-irradiated materials from nanoindentation tests: A case study in proton-irradiated vanadium [J].
Chen, Shang ;
Yuan, Jiuxi ;
Wang, Shumin ;
Mei, Luyao ;
Yan, Jiaohui ;
Li, Lei ;
Zhang, Qiuhong ;
Zhu, Zhixi ;
Lv, Jin ;
Xue, Yunfei ;
Dou, Yankun ;
Xiao, Xiazi ;
Guo, Xun ;
Jin, Ke .
INTERNATIONAL JOURNAL OF PLASTICITY, 2023, 171
[10]   New interatomic potentials of W, Re and W-Re alloy for radiation defects [J].
Chen, Yangchun ;
Li, Yu-Hao ;
Gao, Ning ;
Zhou, Hong-Bo ;
Hu, Wangyu ;
Lu, Guang-Hong ;
Gao, Fei ;
Deng, Huiqiu .
JOURNAL OF NUCLEAR MATERIALS, 2018, 502 :141-153