Micropillar compression study on heavy ion irradiated Zr-2.5Nb pressure tube alloy
Source abstract
Abstract
Abstract In this paper, 40 MeV Zr ion irradiation of Zr-2.5Nb pressure tube alloy was carried out, delivering a damage layer 6.5 μm deep. Uniaxial micropillar compression experiments along the tube axial (AD) and transverse directions (TD) were conducted. Irradiation was found to alter the deformation mechanisms and to increase the yield strength more in the AD oriented pillars than TD pillars for irradiation up to 0.6 dpa. This anisotropy in response is discussed in terms of the limitations of the micropillar compression method and the different deformation mechanisms which are activated in each orientation. The anisotropic hardening effect of -type dislocation loops on prismatic , basal , and pyramidal slip systems is also discussed. The micropillar compression results were also compared with nanoindentation results conducted on the same material.
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Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · High-Velocity Impact and Material Behavior
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References (76)
Show source-provided references
1. Microstructural and microchemical studies of Zr-2.5Nb pressure tube alloy10.1016/0022-3115(93)90087-F ↗
2. Dislocation structure evolution induced by irradiation and plastic deformation in the Zr – 2.5Nb nuclear structural material determined by neutron diffraction line profile analysis10.1016/j.actamat.2012.06.062 ↗
3. Effect of neutron irradiation on deformation mechanisms operating during tensile testing of Zr-2.5Nb10.1016/j.actamat.2015.09.032 ↗
4. Deformation mechanism study of a hot rolled Zr-2.5Nb alloy by transmission electron microscopy. II. In situ transmission electron microscopy study of deformation mechanism change of a Zr-2.5Nb alloy upon heavy ion irradiation10.1063/1.4913614 ↗
5. In situ TEM study on elastic interaction between a prismatic loop and a gliding dislocation10.1016/j.jnucmat.2011.12.001 ↗
6. Challenges to the use of ion irradiation for emulating reactor irradiation10.1557/jmr.2015.73 ↗
7. Heavy-ion irradiation of nickel and nickel alloys10.1080/01418618108239507 ↗
8. TEM characterization of in-reactor neutron irradiated CANDU spacer material Inconel X-75010.1016/j.jnucmat.2014.03.043 ↗
9. Microstructural evolution of CANDU spacer material Inconel X-750 under in situ ion irradiation10.1016/j.jnucmat.2013.06.034 ↗
10. TEM, XRD and nanoindentation characterization of Xenon ion irradiation damage in austenitic stainless steels10.1016/j.jnucmat.2014.07.033 ↗
11. TEM observations and finite element modelling of channel deformation in pre-irradiated austenitic stainless steels - interactions with free surfaces and grain boundaries10.1016/j.jnucmat.2010.01.027 ↗
12. Nishioka · 2016 · 3131
13. Dong · 2017
14. Effect of heavy ion irradiation on microstructure of zirconium alloy characterised by X-ray diffraction10.1016/j.jnucmat.2007.03.217 ↗
15. Heavy ion irradiation induced dislocation loops in AREVA's M5 alloy10.1016/j.jnucmat.2012.01.002 ↗
16. Emulation of reactor irradiation damage using ion beams10.1016/j.scriptamat.2014.06.003 ↗
17. In situ study of defect accumulation in zirconium under heavy ion irradiation10.1016/j.jnucmat.2012.09.014 ↗
18. Accumulation of dislocation loops in the α phase of Zr Excel alloy under heavy ion irradiation10.1016/j.jnucmat.2017.04.038 ↗
19. A review of microstructure evolution in zirconium alloys during irradiation10.1016/0022-3115(88)90093-1 ↗
20. In situ TEM characterisation of dislocation interactions in α-titanium10.1080/14786435.2016.1170222 ↗
21. In situ transmission electron microscopy deformation of the titanium alloy Ti-6Al-4V: interface behaviour10.1016/j.msea.2006.10.183 ↗
22. In situ TEM compression testing of Mg and Mg-0.2 wt.% Ce single crystals10.1016/j.scriptamat.2010.09.047 ↗
23. Nanoindentation and in situ microcompression in different dose regimes of proton beam irradiated 304 SS10.1016/j.jnucmat.2017.01.036 ↗
24. Understanding the effects of ion irradiation using nanoindentation techniques10.1016/j.jnucmat.2014.11.066 ↗
25. Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffraction10.1016/j.jnucmat.2014.11.050 ↗
26. Study of the effect of a irradiation on the microstructure and mechanical properties of nanocrystalline Ni10.1016/j.actamat.2013.02.014 ↗
27. A mechanistic model for depth-dependent hardness of ion irradiated metals10.1016/j.jnucmat.2016.12.039 ↗
28. 〈a〉 Prismatic, 〈a〉 basal, and 〈c+a〉 slip strengths of commercially pure Zr by micro-cantilever tests10.1016/j.actamat.2015.06.020 ↗
29. A study of dislocation transmission through a grain boundary in hcp Ti–6Al using micro-cantilevers10.1016/j.actamat.2015.10.023 ↗
30. Sample dimensions influence strength and crystal plasticity10.1126/science.1098993 ↗
31. The design of accurate micro-compression experiments10.1016/j.scriptamat.2005.06.043 ↗
32. Development and testing of microcompression for post irradiation characterization of ODS steels10.1016/j.jnucmat.2013.09.025 ↗
33. Compressive properties of ‹110› Cu micro-pillars after high-dose self-ion irradiation10.1080/21663831.2013.859179 ↗
34. In situ deformation in T.E.M.: recent developments10.1051/mmm:0199300402-3015300 ↗
35. The plastic zone size in indentation experiments: the analogy with the expansion of a spherical cavity10.1016/j.ijsolstr.2005.07.002 ↗
36. Anisotropic deformation of Zr ion irradiated Zr-2.5%Nb micro-pillars at 25 °C10.1016/j.jnucmat.2011.11.054 ↗
37. James F. Ziegler, The Stopping and Range of Ions in Matter Software, (n.d.). http://www.srim.org/.
38. Evolution of microstructure during fabrication of Zr-2.5 Wt pct Nb alloy pressure tubes10.1007/BF02669427 ↗
39. On the use of SRIM for computing radiation damage exposure10.1016/j.nimb.2013.05.008 ↗
40. Study of defect evolution by TEM with in situ ion irradiation and coordinated modeling10.1080/14786435.2012.662601 ↗
41. Microcompression study of Mg (0001) single crystal10.1016/j.scriptamat.2009.12.048 ↗
42. The relation between load and penetration in the axisymmetric boussinesq problem for a punch of arbitrary profile10.1016/0020-7225(65)90019-4 ↗
43. Constitutive equations for a modified Zr-2.5wt.%Nb pressure tube material10.1016/0921-5093(92)90007-N ↗
44. Size-affected single-slip behavior of pure nickel microcrystals10.1016/j.actamat.2005.05.023 ↗
45. Temperature-dependent size effects on the strength of Ta and W micropillars10.1016/j.actamat.2015.10.016 ↗
46. Plasticity of micrometer-scale single crystals in compression10.1146/annurev-matsci-082908-145422 ↗
47. Effects of focused ion beam milling on the compressive behavior of directionally solidified micropillars and the nanoindentation response of an electropolished surface10.1016/j.actamat.2008.09.033 ↗
48. Direct patterning of gold oxide thin films by focused ion-beam irradiation10.1007/s003390000598 ↗
49. Source-controlled yield and hardening of Cu ( 1 0 0 ) studied by in situ transmission electron microscopy10.1016/j.actamat.2010.10.065 ↗
50. Size dependence of mechanical properties of gold at the micron scale in the absence of strain gradients10.1016/j.actamat.2004.12.031 ↗
51. Anisotropy, size, and aspect ratio effects on micropillar compression of Al[sbnd]SiC nanolaminate composites10.1016/j.actamat.2016.05.018 ↗
52. Dislocation structures and their relationship to strength in deformed nickel microcrystals10.1016/j.actamat.2008.02.046 ↗
53. Anisotropy of yielding in a Zr-2.5Nb pressure tube material10.1007/s11661-000-0278-9 ↗
54. Effects of the initial dislocation density on size effects in single-crystal magnesium10.1016/j.actamat.2013.03.019 ↗
55. Size effects in Al nanopillars: single crystalline vs. bicrystalline10.1016/j.actamat.2011.03.065 ↗
56. High-strength, creep-resistant excel pressure tubes
57. Mechanical annealing and source-limited deformation in submicrometre-diameter Ni crystals10.1038/nmat2085 ↗
58. Rao · 2007 · 37
59. Analysis of steady-state thermal creep of Zr-2.5Nb pressure tube material10.1007/s11661-002-0212-4 ↗
60. Q. Wang, L. Balogh, H.K. Zhang, Y. Zhongwen, M.R. Daymond, Effects of Heavy Ion Irradiation on Zr-2.5Nb Pressure Tube Alloy, Part 2 Orientation Dependent Dislocation Loop Propagation and Elemental Redistribution, submitted to J. Applied Physics.
61. A statistical TEM investigation of dislocation channeling mechanism in neutron irradiated zirconium alloys10.1016/j.jnucmat.2004.04.337 ↗
62. Evolution of interphase and intergranular stresses in Zr-2.5Nb during room temperature deformation10.1016/j.msea.2008.10.016 ↗
63. Deformation behavior of irradiated Zr-2.5Nb pressure tube material10.1007/BF02646682 ↗
64. Deformation mechanisms, texture, and mechanical anisotropy in zirconium and zirccloy
65. Dislocation avalanches, strain bursts, and the problem of plastic forming at the micrometer scale10.1126/science.1143719 ↗
66. On dislocation interaction with radiation-induced defect clusters and plastic flow localization in fcc metals10.1080/01418610108216667 ↗
67. In situ nanocompression testing of irradiated copper10.1038/nmat3055 ↗
68. On the state of deformation in a polycrystalline material in three-dimension: elastic strains, lattice rotations, and deformation mechanisms10.1016/j.ijplas.2018.03.006 ↗
69. Characterization of dislocation substructures in Zr-2.5 Nb pressure tube alloys10.1179/cmq.1985.24.3.253 ↗
70. High-temperature mechanical behavior of cold-worked stress-relieved Zr-2.5Nb10.1007/BF02649594 ↗
71. Deformation mechanism study of a hot rolled Zr-2.5Nb alloy by transmission electron microscopy. I. Dislocation microstructures in as-received state and at different plastic strains
72. Prismatic slip in zirconium single crystals at elevated temperatures10.1007/BF02658531 ↗
73. Comparative study of the deformation behaviour of Zr-2.5 wt% Nb and excel pressure tube alloys10.1179/cmq.1985.24.3.259 ↗
74. Q. Wang, F. Long, Z. Wang, N. Guo, M.R. Daymond, Orientation Dependent Evolution of Plasticity of Irradiated Zr-2.5Nb Pressure Tube Alloy Studied by Nanoindentation and Finite Element Modeling, submitted to J. Nuclear Materials.
75. Modelling flow and work hardening behaviour of cold worked Zr-2.5Nb pressure tube material in the temperature range of 30-600 °C10.1016/j.nucengdes.2013.08.006 ↗
76. Computational modeling of the forward and reverse problems in instrumented sharp indentation10.1016/S1359-6454(01)00295-6 ↗