Capture efficiencies of point defects by 1/2 〈111〉 edge dislocations in tungsten using atomistic simulations
Source abstract
Abstract
We systematically study the interaction behaviors between a point defect (PD) and two types of 1/2 〈111〉 {110} and 1/2 〈111〉 {112} edge dislocations using molecular dynamics (MD), elastic dipole tensor, and kinetic Monte Carlo (KMC) methods in tungsten (W). We first determine the capture region of a vacancy and four types of self-interstitial atoms (SIAs) by calculating their binding energies to both edge dislocations using MD. We then find anisotropic distributions of the diffusion energy barriers of PDs in dislocation systems employing the MD and elastic dipole tensor methods. Subsequently, we utilize the KMC method to obtain the lifetime of PDs and calculate the capture efficiencies of both edge dislocations to PDs at various temperatures and dislocation densities. Results show the capture efficiency of a vacancy decreases with increasing temperature, while it first increases and then decreases with increasing temperature for SIAs. As dislocation density increases, the capture efficiency of PDs increases. Ultimately, the swelling rate is estimated based on the capture efficiency and falls within the range of experimental data. The swelling rate increases first and then decreases with increasing temperature, and the maximum swelling rate occurs around 1200 K, while it increases with increasing the dislocation density. The present results are critical for understanding the interaction behaviors between PDs and 1/2 〈111〉 edge dislocations in W, which provide an essential database for large-scale simulation methods such as rate theory and phase-field simulations.
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Research context
OpenAlex topics: Microstructure and mechanical properties · Fusion materials and technologies · Nuclear Materials and Properties
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (57)
Show source-provided references
1. Neutron irradiation effects on tungsten materials10.1016/j.fusengdes.2014.04.035 ↗
2. Plasma facing and high heat flux materials-needs for ITER and beyond10.1016/S0022-3115(02)01175-3 ↗
3. Key mechanistic features of swelling and blistering of helium-ion-irradiated tungsten10.1016/j.scriptamat.2019.11.039 ↗
4. Defect evolution in single crystalline tungsten following low temperature and low dose neutron irradiation10.1016/j.jnucmat.2015.12.040 ↗
5. The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets10.1088/1361-6587/aaaf62 ↗
6. The effect of high-flux H plasma exposure with simultaneous transient heat loads on tungsten surface damage and power handling10.1088/0029-5515/54/12/123010 ↗
7. Cascade fragmentation: deviation from power law in primary radiation damage10.1080/21663831.2017.1294117 ↗
8. Displacement cascades and defect annealing in tungsten, Part II: object kinetic Monte Carlo simulation of tungsten cascade aging10.1016/j.jnucmat.2014.09.067 ↗
9. Simulation of displacement cascades in tungsten irradiated by fusion neutrons10.1016/j.nimb.2011.01.010 ↗
10. The damage and recovery of neutron irradiated tungsten10.1080/14786436008235842 ↗
11. Irradiation damage and recovery in molybdenum and tungsten
12. Neutron irradiation and defect recovery of tungsten10.1016/0022-3115(70)90193-5 ↗
13. Direct observation of mono-vacancy and self-interstitial recovery in tungsten10.1063/1.5082150 ↗
14. Anisotropic interaction between self-interstitial atoms and 1/2<111>dislocation loops in tungsten10.1007/s11433-020-1676-y ↗
15. Structures and transitions in bcc tungsten grain boundaries and their role in the absorption of point defects10.1016/j.actamat.2018.07.051 ↗
16. Effect of grain boundary character on sink efficiency10.1016/j.actamat.2012.08.009 ↗
17. Effects of grain boundaries on irradiation-induced defects in tungsten by molecular dynamics simulations10.1007/s42243-018-0020-8 ↗
18. Revealing the synergistic effects of sequential and simultaneous dual beam irradiations in tungsten via in-situ TEM10.1016/j.jnucmat.2020.152150 ↗
19. Molecular dynamics simulations of high-dose damage production and defect evolution in tungsten10.1016/j.jnucmat.2021.153158 ↗
20. Bhattacharya · 2020 · 406
21. Loop and void damage during heavy ion irradiation on nanocrystalline and coarse grained tungsten: microstructure, effect of dpa rate, temperature, and grain size10.1016/j.actamat.2018.02.035 ↗
22. Swelling in neutron irradiated tungsten and tungsten-25 percent rhenium10.1016/0036-9748(74)90304-4 ↗
23. Effect of anisotropy, SIA orientation, and one-dimensional migration mechanisms on dislocation bias calculations in metals10.1016/j.jnucmat.2013.02.083 ↗
24. Dislocation bias calculations in metals using a combined finite-element rate-theory approach
25. Sink strength calculations of dislocations and loops using OKMC10.1016/j.jnucmat.2013.08.052 ↗
26. Kinetic Monte-Carlo simulation of self-point defect diffusion in dislocation elastic fields in bcc iron and vanadium10.1016/j.jnucmat.2010.12.176 ↗
27. Elastic modeling of point-defects and their interaction10.1016/j.commatsci.2018.01.053 ↗
28. Capture efficiency and bias from the defect dynamics near grain boundaries in BCC Fe using mesoscale simulations10.1016/j.jmst.2021.02.046 ↗
29. Using lifetime of point defects for dislocation bias in bcc Fe10.1016/j.cossms.2022.101021 ↗
30. Dislocation loop bias and void swelling in irradiated α-iron from mesoscale and atomistic simulations10.1038/s43246-023-00356-5 ↗
31. Defect distribution in ion-irradiated pure tungsten at different temperatures10.1016/j.jnucmat.2016.08.029 ↗
32. High temperature annealing of ion irradiated tungsten10.1016/j.actamat.2015.01.067 ↗
33. The influence of the annealing temperature on deuterium retention in self-damaged tungsten
34. Atomistic simulations of the interactions between the 1/2 〈1 1 1〉 {1 1 0} edge dislocations and the intrinsic point defects in tungsten10.1016/j.nimb.2019.07.035 ↗
35. Dislocation–vacancy interactions in tungsten10.1088/0965-0393/19/7/074002 ↗
36. Migration energy barriers and diffusion anisotropy of point defects on tungsten surfaces10.1016/j.commatsci.2020.109893 ↗
37. First-principles study on mono-vacancy self diffusion and recovery in tungsten crystal10.1016/j.fusengdes.2016.02.044 ↗
38. Effect of stress on vacancy formation and migration in body-centered-cubic metals
39. An atomic-level model for studying the dynamics of edge dislocations in metals10.1088/0965-0393/11/4/302 ↗
40. Interatomic potentials for modelling radiation defects and dislocations in tungsten
41. Embedded-atom method potential for modeling hydrogen and hydrogen-defect interaction in tungsten
42. https://www.lammps.org/.
43. Time evolution of a quenched binary alloy. III. Computer simulation of a two-dimensional model system10.1103/PhysRevB.13.4328 ↗
44. Monte Carlo studies of vacancy migration in binary ordered alloys: I10.1088/0370-1328/89/3/329 ↗
45. A new algorithm for Monte Carlo simulation of king spin systems10.1016/0021-9991(75)90060-1 ↗
46. Golubov · 2012 · 357
47. Golubov · 2020 · 717
48. Sink strength and dislocation bias of three-dimensional microstructures
49. Displacement cascades and defects annealing in tungsten, Part I: defect database from molecular dynamics simulations10.1016/j.jnucmat.2014.12.056 ↗
50. First-principles study of vacancy, interstitial, noble gas atom interstitial and vacancy clusters in bcc-W10.1016/j.commatsci.2016.06.022 ↗
51. Stability and mobility of rhenium and osmium in tungsten: first principles study10.1088/0965-0393/22/7/075006 ↗
52. Elastic fields, dipole tensors, and interaction between self-interstitial atom defects in bcc transition metals
53. Universality of point defect structure in body-centered cubic metals
54. Microstructure development of dispersion-strengthened tungsten due to neutron irradiation10.1016/j.jnucmat.2013.10.012 ↗
55. New insights into microstructure of neutron-irradiated tungsten10.1038/s41598-021-86746-6 ↗
56. First-principles study on migration of vacancy in tungsten10.1585/pfr.9.3401117 ↗
57. Modeling fast neutron irradiation damage accumulation in tungsten10.1016/j.jnucmat.2012.06.019 ↗