Temperature and radiation effects on brittle versus ductile fracture behavior in miscible phase boundaries: insight from atomistic simulations
Source abstract
Abstract
Temperature- and irradiation-assisted failure mechanisms in miscible phase boundaries are clarified via atomistic calculations. We first establish the temperature-dependent brittle-to-ductile transition in U–Zr miscible phase boundaries. Our results confirm that these boundaries are mostly brittle at low temperatures and ductile at elevated temperatures. We then investigate the changes induced by irradiation on the fracture mechanisms in such phase boundaries. The irradiation-induced defect accumulation follows a multi-stage process that starts with the accumulation of isolated small dislocation loops before transitioning to the saturation and growth of larger dislocation loops and end up with a reorganization into forest dislocations. The accumulation of loops is the primary feature to participate in the delineation between brittle and ductile interfacial fracture in irradiated phase boundaries. At low damage levels, radiation defect interactions with the crack tip are limited and U–Zr miscible boundaries fail through the emission of dislocations ahead of the crack tip followed by brittle cleavage in agreement with the classical Griffith’s criterion for crack stability. At higher damage levels, the failure mode transitions from brittle crack growth to ductile void growth. In this case, the microcrack tip is blunted by the high density of pre-existing, radiation-induced defects in the vicinity of the crack. This interaction leads to the development and growth of a cavity at the interface as opposed to interfacial cleavage.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear materials and radiation effects
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (45)
Show source-provided references
1. Arjhangmehr A, Feghhi SAH (2016) Irradiation deformation near different atomic grain boundaries in $$\alpha $$-Zr: an investigation of thermodynamics and kinetics of point defects. Sci Rep 6:23333. https://doi.org/10.1038/srep2333310.1038/srep23333 ↗
2. Barrows W, Dingreville R, Spearot DS (2016) Traction-separation relationships for hydrogen induced grain boundary embrittlement in nickel via molecular dynamics simulations. Mater Sci Eng A 650:354–364. https://doi.org/10.1016/j.msea.2015.10.04210.1016/j.msea.2015.10.042 ↗
3. Basak C, Prasad GJ, Kamath HS, Prabhu N (2009) An evaluation of the properties of as-cast U-rich U–Zr alloys. J Alloy Compd 480(2):857–862. https://doi.org/10.1016/j.jallcom.2009.02.07710.1016/j.jallcom.2009.02.077 ↗
4. Beyerlein I, Demkowicz M, Misra A, Uberuaga BP (2015) Defect–interface interactions. Prog Mater Sci 74:125–210. https://doi.org/10.1016/j.pmatsci.2015.02.00110.1016/j.pmatsci.2015.02.001 ↗
5. Brinkman JA (1954) On the nature of radiation damage in metals. J Appl Phys 25(8):961–970. https://doi.org/10.1063/1.172181010.1063/1.1721810 ↗
6. Bruemmer SM, Simonen EP, Scott PM, Andresen PL, Was GS, Nelson JL (1999) Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals. J Nucl Mater 274(3):299–314. https://doi.org/10.1016/S0022-3115(99)00075-610.1016/S0022-3115(99)00075-6 ↗
7. Chartier A, Marinica M-C (2019) Rearrangement of interstitial defects in alpha-Fe under extreme condition. Acta Mater 180:141–148. https://doi.org/10.1016/j.actamat.2019.09.00710.1016/j.actamat.2019.09.007 ↗
8. Chartier A, Onofri C, Van Brutzel L, Sabathier C, Dorosh O, Jagielski J (2016) Early stages of irradiation induced dislocations in urania. Appl Phys Lett 109:181902. https://doi.org/10.1063/1.496719110.1063/1.4967191 ↗
9. Chen EY, Dingreville R, Deo C (2018) Misfit dislocation networks in semi-coherent miscible phase boundaries: an example for U–Zr interfaces. Comput Mater Sci 154:194–203. https://doi.org/10.1016/j.commatsci.2018.07.06510.1016/j.commatsci.2018.07.065 ↗
10. Chen EY, Deo C, Dingreville R (2019) Irradiation resistance of nanostructured interfaces in Zr-Nb metallic multilayers. J Mater Res 34(13):2239–2251. https://doi.org/10.1557/jmr.2019.4210.1557/jmr.2019.42 ↗
11. Chen E, Deo C, Dingreville R (2020) Reduced-order atomistic method for simulating radiation damage in metals. J Phys 32:045402. https://doi.org/10.1088/1361-648X/ab4b7c10.1088/1361-648X/ab4b7c ↗
12. Collins R (1986) Factors determining radiation-induced mixing at interfaces. Radiat Effects 98(1–4):1–20. https://doi.org/10.1080/0033757860820609210.1080/00337578608206092 ↗
13. Dingreville R, Aksoy D, Spearot DE (2017) A primer on selecting grain boundary sets for comparison of interfacial fracture properties in molecular dynamics simulations. Sci Rep 7(1):8332. https://doi.org/10.1038/s41598-017-08637-z10.1038/s41598-017-08637-z ↗
14. Gumbsch P, Riedle J, Hartmaier A, Fischmeister HF (1998) Controlling factors for the brittle-to-ductile transition in tungsten single crystals. Science 282(5392):1293–1295. https://doi.org/10.1126/science.282.5392.129310.1126/science.282.5392.1293 ↗
15. He M-R, Johnson DC, Was GS, Robertson IM (2017) The role of grain boundary microchemistry in irradiation-assisted stress corrosion cracking of a Fe-13Cr-15Ni alloy. Acta Mater 138:61–71. https://doi.org/10.1016/j.actamat.2017.07.04210.1016/j.actamat.2017.07.042 ↗
16. Hull D, Rimmer DE (1959) The growth of grain-boundary voids under stress. Philos Mag 4(42):673–687. https://doi.org/10.1080/1478643590824326410.1080/14786435908243264 ↗
17. Li N, Martin MS, Anderoglu O, Misra A, Shao L, Wang H, Zhang X (2009) He ion irradiation damage in Al/Nb multilayers. J Appl Phys 105(12):123522. https://doi.org/10.1063/1.313880410.1063/1.3138804 ↗
18. Liu BX, Lai WS, Zhang Q (2000) Irradiation induced amorphization in metallic multilayers and calculation of glass-forming ability from atomistic potential in the binary metal systems. Mater Sci Eng 29(1–2):1–48. https://doi.org/10.1016/S0927-796X(00)00016-410.1016/S0927-796X(00)00016-4 ↗
19. Ludy JE, Rupert TJ (2016) Amorphous intergranular films act as ultra-efficient point defect sinks during collision cascades. Scripta Mater 110:37–40. https://doi.org/10.1016/j.scriptamat.2015.07.04010.1016/j.scriptamat.2015.07.040 ↗
20. Milosavljević M, Stojanović N, Peruško D, Timotijević B, Toprek D, Kovač J, Dražič G, Jeynes C (2012) Ion irradiation induced Al–Ti interaction in nano-scaled Al/Ti multilayers. Appl Surf Sci 258(6):2043–2046. https://doi.org/10.1016/j.apsusc.2011.04.10710.1016/j.apsusc.2011.04.107 ↗
21. Milosavljević M, Toprek D, Obradović M, Grce A, Peruško D, Dražič G, Kovač J, Homewood KP (2013) Ion irradiation induced solid-state amorphous reaction in Ni/Ti multilayers. Appl Surf Sci 268:516–523. https://doi.org/10.1016/j.apsusc.2012.12.15810.1016/j.apsusc.2012.12.158 ↗
22. Miura T, Fujii K, Fukuya K (2015) Micro-mechanical investigation for effects of helium on grain boundary fracture of austenitic stainless steel. J Nucl Mater 457:279–290. https://doi.org/10.1016/j.jnucmat.2014.11.06210.1016/j.jnucmat.2014.11.062 ↗
23. Moore AP, Beeler B, Deo C, Baskes MI, Okuniewski MA (2015) Atomistic modeling of high temperature uranium–zirconium alloy structure and thermodynamics. J Nucl Mater 467:802–819. https://doi.org/10.1016/j.jnucmat.2015.10.01610.1016/j.jnucmat.2015.10.016 ↗
24. Nozawa T, Katoh Y, Snead LL (2009) The effect of neutron irradiation on the fiber/matrix interphase of silicon carbide composites. J Nucl Mater 384(3):195–211. https://doi.org/10.1016/j.jnucmat.2008.11.01510.1016/j.jnucmat.2008.11.015 ↗
25. Okamoto PR, Rehn LE (1979) Radiation-induced segregation in binary and ternary alloys. J Nucl Mater 83(1):2–23. https://doi.org/10.1016/0022-3115(79)90587-710.1016/0022-3115(79)90587-7 ↗
26. Orowan E (1950) Fundamentals of brittle behavior in metals. Wiley, New York
27. Pahl RG, Porter DL, Lahm CE, Hofman GL (1990) Experimental studies of U-Pu-Zr fast reactor fuel pins in the experimental breeder reactor-II. Metall Trans A 21(7):1863–1870. https://doi.org/10.1007/BF0264723310.1007/BF02647233 ↗
28. Plimpton S (1995) Fast parallel algorithms for short-range molecular dynamics. J Comput Phys 117(1):1–19. https://doi.org/10.1006/jcph.1995.103910.1006/jcph.1995.1039 ↗
29. Rice JR, Thomson R (1974) Ductile versus brittle behaviour of crystals. Philos Mag 29(1):73–97. https://doi.org/10.1080/1478643740821355510.1080/14786437408213555 ↗
30. Sand AE, Dequeker J, Becquart CS, Domain C, Nordlund K (2016) Non-equilibrium properties of interatomic potentials in cascade simulations in tungsten. J Nucl Mater 470:119–127. https://doi.org/10.1016/j.jnucmat.2015.12.01210.1016/j.jnucmat.2015.12.012 ↗
31. Schoeck G (1991) Dislocation emission from crack tips. Philos Mag A 63(1):111–120. https://doi.org/10.1080/0141861910820459610.1080/01418619108204596 ↗
32. Sickafus KE, Matzke H, Hartmann T, Yasuda K, Valdez JA, Chodak P III, Nastasi M, Verrall RA (1999) Radiation damage effects in zirconia. J Nucl Mater 274(1–2):66–77. https://doi.org/10.1016/S0022-3115(99)00041-010.1016/S0022-3115(99)00041-0 ↗
33. Snead LL, Osborne M, More KL (1995) Effects of radiation on SiC-based Nicalon fibers. J Mater Res 10(3):736–747. https://doi.org/10.1557/JMR.1995.073610.1557/JMR.1995.0736 ↗
34. Söderlind P (2002) First-principles elastic and structural properties of uranium metal. Phys Rev B 66(8):085113. https://doi.org/10.1103/PhysRevB.66.08511310.1103/PhysRevB.66.085113 ↗
35. Stukowski A (2010) Visualization and analysis of atomistic simulation data with OVITO—the Open Visualization Tool. Modell Simul Mater Sci Eng 18(1):015012. https://doi.org/10.1088/0965-0393/18/1/01501210.1088/0965-0393/18/1/015012 ↗
36. Stukowski A, Bulatov VV, Arsenlis A (2012) Automated identification and indexing of dislocations in crystal interfaces. Modell Simul Mater Sci Eng 20(8):085007. https://doi.org/10.1088/0965-0393/20/8/08500710.1088/0965-0393/20/8/085007 ↗
37. Uberuaga BP, Vernon LJ, Martinez E, Voter AF (2015) The relationship between grain boundary structure, defect mobility, and grain boundary sink efficiency. Sci Rep 5:9095. https://doi.org/10.1038/srep0909510.1038/srep09095 ↗
38. Vattré AJ, Abdolrahim N, Kolluri K, Demkowicz MJ (2014) Computational design of patterned interfaces using reduced order models. Sci Rep 4:6231. https://doi.org/10.1038/srep0623110.1038/srep06231 ↗
39. Vítek V (1968) Intrinsic stacking faults in body-centred cubic crystals. Philos Mag 18(154):773–786. https://doi.org/10.1080/1478643680822750010.1080/14786436808227500 ↗
40. Was GS (2016) Fundamentals of radiation materials science: metals and alloys. Springer, New York, NY. https://doi.org/10.1007/978-1-4939-3438-610.1007/978-1-4939-3438-6 ↗
41. Weertman J (1974) Theory of high temperature intercrystalline fracture under static or fatigue loads, with or without irradiation damage. Metall Trans 5(8):1743–1751. https://doi.org/10.1007/BF0264413610.1007/BF02644136 ↗
42. Willaime F, Massobrio C (1991) Development of an n-body interatomic potential for hcp and bcc zirconium. Phys Rev B 43(14):11653. https://doi.org/10.1103/PhysRevB.43.1165310.1103/PhysRevB.43.11653 ↗
43. Wronski AS, Chilton AC, Capron EM (1969) The ductile-brittle transition in polycrystalline molybdenum. Acta Metall 17(6):751–755. https://doi.org/10.1016/0001-6160(69)90081-910.1016/0001-6160(69)90081-9 ↗
44. Yamakov V, Saether E, Phillips DR, Glaessgen EH (2006) Molecular-dynamics simulation-based cohesive zone representation of intergranular fracture processes in aluminum. J Mech Phys Solids 54(9):1899–1928. https://doi.org/10.1016/j.jmps.2006.03.00410.1016/j.jmps.2006.03.004 ↗
45. Ziegler JF, Ziegler MD, Biersack JP (2010) SRIM-The stopping and range of ions in matter. Nucl Instrum Methods Phys Res Sect B 268(11–12):1818–1823. https://doi.org/10.1016/j.nimb.2010.02.09110.1016/j.nimb.2010.02.091 ↗