journal article·2016-05Open access

Identification of dominant damage accumulation processes at grain boundaries during irradiation in nanocrystalline α-Fe: A statistical study

Aaron Dunn, Rémi Dingreville, Enrique Martínez, Laurent Capolungo

Acta Materialia· Volume 110

Abstract

Abstract Radiation defect accumulation in metals with high interface to volume ratios, such as nanocrystalline metals, is strongly dependent on the ability of these interfaces to act as unbiased sinks for defects. Multi-scale simulations of damage accumulation in such materials necessarily depend on parameters describing defect behaviors inside grain boundaries, such as migration and binding energies within grain boundaries as well as binding energies of defects to grain boundaries. In general, these behaviors are sensitive to the grain boundary structure, making atomic-scale quantification of such parameters challenging due to the large number of variables in the input space of such a problem. The goal of the present study is to identify which of these parameters most strongly influence defect accumulation and grain boundary sink efficiency in α-Fe during Frenkel pair implantation at room temperature and a dose rate of 10−7 dpa⋅ s−1. Defect accumulation inside grains and in grain boundaries is simulated using spatially resolved stochastic cluster dynamics (SRSCD). Using this methodology, sensitivity studies investigating vacancy accumulation in grain boundaries, sink efficiency η of grain boundaries, and vacancy cluster profiles inside grains are performed by varying model input parameters such as defect migration and binding energies inside grain boundaries. Principal component analysis of these model input parameters is then carried out to identify which defect behaviors are strongly correlated with changes in damage accumulation metrics when varying many parameters at once. In both of these analyses, single vacancy and self-interstitial diffusion inside grain boundaries, small vacancy cluster diffusion inside grain boundaries, and the binding energy of vacancies and self-interstitials to grain boundaries are shown to have the greatest impact on defect accumulation.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Fusion materials and technologies · Nuclear Materials and Properties · Nuclear materials and radiation effects

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (71)

Show source-provided references
1. Carew · 1997
2. Operating temperature windows for fusion reactor structural materials10.1016/S0920-3796(00)00320-3 ↗
3. Irradiation-induced micro structural changes, and hardening mechanisms, in model PWR reactor pressure vessel steels10.1016/0022-3115(95)00026-7 ↗
4. Evolution of nuclear fission reactors: third generation and beyond10.1016/j.enconman.2009.12.043 ↗
5. Materials for the plasma-facing components of fusion reactors10.1016/j.jnucmat.2004.04.005 ↗
6. Analysis of displacement damage in materials in nuclear fusion facilities (DEMO, IFMIF and TechnoFusion)10.1016/j.fusengdes.2010.12.041 ↗
7. Voids in irradiated stainless steel10.1038/216575a0 ↗
8. Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel10.1016/0022-3115(93)90128-L ↗
9. Structure and metastability of mesoscopic vacancy and interstitial loop defects in iron and tungsten10.1088/0953-8984/20/34/345214 ↗
10. Story of stacking fault tetrahedra10.1016/S0254-0584(97)80250-7 ↗
11. Defect production, annealing kinetics and damage evolution in α-Fe: an atomic-scale computer simulation10.1080/01418619808239970 ↗
12. Energetics of formation and migration of self-interstitials and self-interstitial clusters in α-iron10.1016/S0022-3115(96)00736-2 ↗
13. Analysis of displacement damage and defect production under cascade damage conditions10.1016/0022-3115(93)90140-T ↗
14. Microstructure of neutron-irradiated iron before and after tensile deformation10.1016/j.jnucmat.2006.02.031 ↗
15. Dose dependence of defect accumulation in neutron irradiated copper and iron10.1016/S0022-3115(02)01160-1 ↗
16. Irradiation hardening behavior of polycrystalline metals after low temperature irradiation10.1016/j.jnucmat.2003.12.012 ↗
17. Cascade damage effects on the swelling of irradiated materials
18. Void migration, coalescence and swelling in fusion materials10.1016/S0920-3796(03)00299-0 ↗
19. Theory and experimental background on dimensional changes in irradiated alloys10.1016/0022-3115(94)90009-4 ↗
20. On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels10.1016/0036-9748(83)90280-6 ↗
21. Embrittlement of nuclear reactor pressure vessels10.1007/s11837-001-0081-0 ↗
22. Advanced materials for fusion technology10.1016/j.fusengdes.2005.08.008 ↗
23. The challenge of developing structural materials for fusion power systems10.1016/S0022-3115(98)00352-3 ↗
24. Perspective of ODS alloys application in nuclear environments10.1016/S0022-3115(02)01043-7 ↗
25. Recent developments in irradiation-resistant steels10.1146/annurev.matsci.38.060407.130315 ↗
26. Radiation damage tolerant nanomaterials10.1016/j.mattod.2013.10.019 ↗
27. Interface structure and radiation damage resistance in Cu-Nb multilayer nanocomposites10.1103/PhysRevLett.100.136102 ↗
28. The radiation damage tolerance of ultra-high strength nanolayered composites10.1007/s11837-007-0120-6 ↗
29. Atomic-scale design of radiation-tolerant nanocomposites10.1557/mrs2010.704 ↗
30. Are nanoporous materials radiation resistant?10.1021/nl201383u ↗
31. Surface effects on the radiation response of nanoporous Au foams10.1063/1.4764528 ↗
32. Enhanced radiation tolerance of ultrafine grained Fe–Cr–Ni alloy10.1016/j.jnucmat.2011.10.001 ↗
33. Development of ultra-fine grained W–(0.25–0.8) wt% TiC and its superior resistance to neutron and 3MeV He-ion irradiations10.1016/j.jnucmat.2008.02.055 ↗
34. Effect of grain boundary character on sink efficiency10.1016/j.actamat.2012.08.009 ↗
35. Bubble formation at grain boundaries in helium implanted copper10.1016/j.scriptamat.2004.05.038 ↗
36. Vacancy loss at grain boundaries in quenched polycrystalline gold10.1016/0001-6160(80)90159-5 ↗
37. Point defect annihilation at grain boundaries in gold10.1016/0036-9748(85)90118-8 ↗
38. Probing grain boundary sink strength at the nanoscale: Energetics and length scales of vacancy and interstitial absorption by grain boundaries in α-Fe10.1103/PhysRevB.85.064108 ↗
39. B. P. Uberuaga, L. J. Vernon, E. Martinez, A. F. Voter, The relationship between grain boundary structure, defect mobility, and grain boundary sink efficiency, Sci. Rep.. 5..10.1038/srep09095 ↗
40. Mean field rate theory and object kinetic Monte Carlo: a comparison of kinetic models10.1016/j.jnucmat.2008.08.047 ↗
41. Simulation of defect evolution in irradiated materials: role of intracascade clustering and correlated recombination10.1103/PhysRevB.75.184101 ↗
42. Rate theory cluster dynamics simulations including spatial correlations within displacement cascades10.1103/PhysRevB.86.054113 ↗
43. Cluster-dynamics modelling of defects in α-iron under cascade damage conditions10.1016/j.jnucmat.2008.08.010 ↗
44. Modeling the long-term evolution of the primary damage in ferritic alloys using coarse-grained methods10.1016/j.jnucmat.2010.05.019 ↗
45. Modeling the microstructural evolution in bcc-Fe during irradiation using kinetic monte carlo computer simulation10.1016/j.jnucmat.2003.08.021 ↗
46. Simulation of the nanostructure evolution under irradiation in Fe–C alloys10.1016/j.jnucmat.2013.07.046 ↗
47. OKMC simulations of Fe–C systems under irradiation: sensitivity studies10.1016/j.jnucmat.2014.05.011 ↗
48. Cluster dynamics modeling of accumulation and diffusion of helium in neutron irradiated tungsten10.1016/j.jnucmat.2011.12.015 ↗
49. A rate theory study of helium bubble formation and retention in Cu–Nb nanocomposites10.1016/j.jnucmat.2012.12.041 ↗
50. Modeling spatially dependent kinetics of helium desorption in BCC iron following He ion implantation10.1016/j.jnucmat.2010.06.025 ↗
51. He diffusion in irradiated α-Fe: an ab-initio-based rate theory model10.1103/PhysRevB.75.100102 ↗
52. Molecular-dynamics studies of grain-boundary diffusion. II. Vacancy migration, diffusion mechanism, and kinetics10.1103/PhysRevB.29.5363 ↗
53. Grain boundary diffusion mechanisms in metals10.1007/BF02648378 ↗
54. Diffusion mechanisms in Cu grain boundaries10.1103/PhysRevB.62.3658 ↗
55. Uranium vacancy mobility at the Σ 5 symmetric tilt and Σ 5 twist grain boundaries in UO 210.1016/j.commatsci.2015.06.017 ↗
56. Spatially resolved stochastic cluster dynamics for radiation damage evolution in nanostructured metals10.1016/j.jnucmat.2013.07.009 ↗
57. Multiscale modelling of defect kinetics in irradiated iron10.1038/nmat1286 ↗
58. Migration kinetics of the self-interstitial atom and its clusters in bcc Fe10.1080/01418610108214307 ↗
59. Simulating radiation damage accumulation in α-Fe: a spatially resolved stochastic cluster dynamics approach10.1016/j.commatsci.2015.02.041 ↗
60. Formation of stable sessile interstitial complexes in reactions between glissile dislocation loops in bcc Fe10.1016/j.jnucmat.2008.08.031 ↗
61. Interstitials and Vacancies in α Iron10.1103/PhysRev.134.A1329 ↗
62. The theory of sink strengths10.1098/rsta.1981.0158 ↗
63. A general method for numerically simulating the stochastic time evolution of coupled chemical reactions10.1016/0021-9991(76)90041-3 ↗
64. 1D to 3D diffusion-reaction kinetics of defects in crystals10.1103/PhysRevB.66.060105 ↗
65. Comparative study of radiation damage accumulation in Cu and Fe10.1016/S0022-3115(99)00220-2 ↗
66. Synchronous parallel kinetic Monte Carlo for continuum diffusion-reaction systems10.1016/j.jcp.2007.11.045 ↗
67. Synchronous parallel spatially resolved stochastic cluster dynamics10.1016/j.commatsci.2015.02.041 ↗
68. Neutron-induced swelling and embrittlement of pure iron and pure nickel irradiated in the BN-350 and BOR-60 fast reactors10.1016/j.jnucmat.2008.01.015 ↗
69. The influence of 3 twin boundaries on the formation of radiation-induced defect clusters in nanotwinned Cu10.1557/jmr.2011.56 ↗
70. Principal component analysis10.1002/wics.101 ↗
71. Jolliffe · 2002