journal article·2024-10

Effect of Fe addition and ion irradiation on surface hardness in zirconium alloys: Experiments and modeling

Liang Xia, Yucheng Cao, Kai Liu, Ding Chen, Chao Jiang

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OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Metal and Thin Film Mechanics

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References (79)

Show source-provided references
1. Effect of hydrogen uptake on the electrochemical corrosion of N18 zircaloy under gamma irradiation10.1016/j.apsusc.2016.01.158 ↗
2. Surface treatment to form a dispersed Y2O3 layer on Zircaloy-4 tubes10.1016/j.apsusc.2017.06.108 ↗
3. Microstructures and corrosion resistance of Zircaloy-4 after surface alloying with copper by high-current pulsed electron beam10.1016/j.apsusc.2019.144222 ↗
4. Analysis method of matrix and second phase particles in Zircaloy-2 by atom probe tomography10.1016/j.pnucene.2014.07.012 ↗
5. The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy10.1016/j.actamat.2017.03.024 ↗
6. Characterization of different forms of Zr-2.5 Nb samples before and after neutron irradiation10.1016/j.msea.2018.01.059 ↗
7. Susceptibility of Zr-2.5 (wt.%) Nb alloy to undergo nodular corrosion in water and steam environments: Effect of surface, cold work, temperature10.1016/j.pnucene.2023.104823 ↗
8. Study of microstructure and precipitates of a Zr-2.5 Nb-0.5 Cu CANDU spacer material10.1016/j.jnucmat.2016.09.017 ↗
9. Precipitate stability in a Zr-2.5Nb-0.5Cu alloy under heavy ion irradiation10.3390/met7080287 ↗
10. Effects of alloying elements (Sn, Nb, Cr, and Mo) on the microstructure and mechanical properties of zirconium alloys10.1080/00223131.2014.996622 ↗
11. The influence of alloying elements on the corrosion of Zr alloys10.1016/j.corsci.2015.12.022 ↗
12. Effects of alloying elements (Sn, Cr and Cu) on second phase particles in Zr-Sn-Nb-Fe-(Cr, Cu) alloys10.1016/j.jallcom.2018.03.203 ↗
13. Zirconium alloys for supercritical water reactor applications: challenges and possibilities10.1016/j.jnucmat.2007.05.022 ↗
14. Effect of Nb and Fe on corrosion resistance of zirconium alloys
15. R. Tewari, K. V. M. Krishna, S. Neogy, C. Lemaignan (2020). 7.08 - Zirconium and its Alloys: Properties and Characteristics. Comprehensive Nuclear Materials (Second Edition). Amsterdam, Netherlands, Elsevier: 284-302.10.1016/B978-0-12-803581-8.11735-7 ↗
16. Influence of Fe content on corrosion and hydrogen pick up behavior of Zr-2.5Nb pressure tube material10.1016/j.jnucmat.2013.05.026 ↗
17. Effect of Fe on the precipitate characteristics and out-of-pile corrosion behavior of Zr-1Nb-xFe alloys10.4028/www.scientific.net/MSF.743-744.1 ↗
18. Influence of ions irradiation on the microstructural evolution, mechanical and tribological properties of Zr-4 alloy10.1016/j.apsusc.2019.143821 ↗
19. Assessment of microstructure, mechanical and tribological properties of Zr-4 alloy after pre-oxidation and ion irradiation10.1016/j.apsusc.2022.155444 ↗
20. Microstructure analysis of Xe20+ irradiation and postirradiation corrosion of Zr-4 and Zr–1Nb alloys10.1016/j.radphyschem.2023.110986 ↗
21. Study on the effect of Ar9+ ion irradiation of Zr–2.5 wt.% Nb alloy pressure tube10.1080/14786435.2018.1543963 ↗
22. Heavy ion irradiation induced dislocation loops in AREVA’s M5® alloy10.1016/j.jnucmat.2012.01.002 ↗
23. Tensile properties and microstructure of Zr–1.8 Nb alloy subjected to 140-MeV C4+ ion irradiation10.1016/j.jnucmat.2017.07.068 ↗
24. Irradiation damage and hardening in pure Zr and Zr-Nb alloys at 573 K from self-ion irradiation10.1016/j.matdes.2018.11.017 ↗
25. A steady-state irradiation creep and thermal creep model for zirconium alloys
26. Effects of heavy ion irradiation on Zr-2.5 Nb pressure tube alloy. I. orientation dependent mechanical response
27. Wear behavior of zirconium-4 alloy after different irradiation damage level10.1016/j.apsusc.2020.145373 ↗
28. The formation of atomic and sub-nano scale pores under tensile strain in oxide films on Zr alloys: a first-principles study10.1016/j.apsusc.2021.151316 ↗
29. Effects of primary α grains on rolling reductions and deformation modes in Zr alloys: experiments and modeling10.1016/j.mechmat.2024.104957 ↗
30. Corrosion protection and failure mechanism of ZrO2 coating on zirconium alloy Zry-4 under varied LiOH concentrations in lithiated water at 360° C/18.5 MPa10.1016/j.apsusc.2023.159173 ↗
31. Indentation size effects in crystalline materials: a law for strain gradient plasticity10.1016/S0022-5096(97)00086-0 ↗
32. A model to evaluate the nano-indentation hardness of ion-irradiated materials10.1016/j.nimb.2014.09.012 ↗
33. Microstructure-informed prediction and measurement of nanoindentation hardness of an Fe-9Cr alloy irradiated with Fe-ions of 1 and 5 MeV energy
34. The role of primary α grains in the degree of transformation texture obeying the burgers orientation relationship in Zr alloys10.1016/j.ijrmhm.2022.105908 ↗
35. Variant selection and morphology by the different cooling rates in Zr-xNb-0.4 Mo alloys10.1016/j.jnucmat.2022.154230 ↗
36. In situ TEM investigation of amorphization and recrystallization of Zr (Fe, Cr, Nb) 2 precipitates under Ne ion irradiation10.1016/j.vacuum.2014.08.002 ↗
37. Ion-irradiation induced hardening behavior of zirconium alloys: a combination of experimental and theoretical study10.1016/j.ijrmhm.2023.106432 ↗
38. Zirconium alloys in nuclear applications
39. Revealing the temperature-dependent hardening mechanisms of non-uniformly distributed defects for ion-irradiated metals: experiments and modeling10.1016/j.msea.2024.146408 ↗
40. SRIM–The stopping and range of ions in matter (2010)10.1016/j.nimb.2010.02.091 ↗
41. Effect of Nb and Fe on damage evolution in a Zr-alloy during proton and neutron irradiation10.1016/j.actamat.2018.12.021 ↗
42. Microstructural evolution and hardening effect of 12Cr2W2Mn ferritic/martensitic steel under Au-ions irradiation10.1016/j.jallcom.2020.155360 ↗
43. An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments10.1557/JMR.1992.1564 ↗
44. Effects of alloying elements on the formation of -component loops in Zr alloy excel under heavy ion irradiation10.1557/jmr.2015.89 ↗
45. Accumulation of dislocation loops in the α phase of Zr excel alloy under heavy ion irradiation10.1016/j.jnucmat.2017.04.038 ↗
46. Effect of the addition of Cu on irradiation induced defects and hardening in Zr-Nb alloys10.1016/j.jnucmat.2019.03.025 ↗
47. Anisotropic distribution of dislocation loops in HVEM-irradiated Zr10.1080/01418618408233290 ↗
48. A review of microstructure evolution in zirconium alloys during irradiation10.1016/0022-3115(88)90093-1 ↗
49. Effects of an alloying element on a c-component loop formation and precipitate resolution in Zr alloys during ion irradiation10.1080/00223131.2018.1486244 ↗
50. Microstructure and mechanical properties of as-cast Zr–Nb alloys10.1016/j.actbio.2011.07.020 ↗
51. Microstructure, mechanical property, corrosion behavior, and in vitro biocompatibility of Zr–Mo alloys10.1002/jbm.b.32833 ↗
52. The Fe− Zr (Iron-Zirconium) system10.1007/BF02881963 ↗
53. Damaged regions in neutron-irradiated and ion-bombarded Ge and Si10.1080/00337577108231056 ↗
54. Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings10.1016/j.anucene.2021.108206 ↗
55. Comparison of linear and square superposition hardening models for the surface nanoindentation of ion-irradiated materials10.1016/j.jnucmat.2018.02.047 ↗
56. Investigation of hardening behavior in Xe ion-irradiated Zr–1Nb10.1016/j.jnucmat.2016.03.003 ↗
57. Orientation-dependent irradiation hardening in pure Zr studied by nanoindentation, electron microscopies, and crystal plasticity finite element modeling10.1016/j.ijplas.2019.08.007 ↗
58. A statistical analysis of strain hardening: The percolation limit and the Taylor equation10.1016/j.actamat.2012.08.008 ↗
59. Plastic zone size for nanoindentation of irradiated Fe-9% Cr ODS10.1016/j.jnucmat.2016.08.033 ↗
60. Model for the hardness-depth relationships of ion-irradiated nanocrystalline metals10.1016/j.jmrt.2023.10.101 ↗
61. M. Ashby (1968). Oxide dispersion strengthening. Proc. 2nd Bolton Landing Conf., GS Ansell, ed., Gordon and Breach, New York, NY, 143.
62. Symposium on internal stresses in metals and alloys
63. Revealing the hardening mechanisms of ion-irradiated nanostructured multilayers/substrate systems: a theoretical model10.1016/j.ijplas.2020.102925 ↗
64. A hardening model considering grain size effect for ion-irradiated polycrystals under nanoindentation10.1016/j.net.2021.03.007 ↗
65. Indentation size effect in metallic materials: correcting for the size of the plastic zone10.1016/j.scriptamat.2005.02.009 ↗
66. A mechanistic model for depth-dependent hardness of ion irradiated metals10.1016/j.jnucmat.2016.12.039 ↗
67. Six decades of the Hall-Petch effect–a survey of grain-size strengthening studies on pure metals10.1080/09506608.2016.1191808 ↗
68. Influence of grain size on the mechanical behaviour of some high strength materials10.1007/BF00547918 ↗
69. Dislocation study of prismatic slip systems and their interactions in hexagonal close packed metals: application to zirconium10.1016/j.actamat.2004.05.048 ↗
70. A dislocation-based constitutive law for pure Zr including temperature effects10.1016/j.ijplas.2007.07.017 ↗
71. A simple theory of static and dynamic hardness10.1098/rspa.1948.0008 ↗
72. Continuum theory of ductile rupture by void nucleation and growth: part I—yield criteria and flow rules for porous ductile media10.1115/1.3443401 ↗
73. High temperature nano-indentation on the mechanical properties of Zr and Zr-Fe alloys: experimental and theoretical analysis10.1016/j.mechmat.2021.104053 ↗
74. On the interaction between slip dislocations and twins in HCP Zr10.1016/j.msea.2009.01.035 ↗
75. The onset of twinning in metals: a constitutive description10.1016/S1359-6454(01)00300-7 ↗
76. Effect of Xe26+ ion irradiation on the microstructural evolution and mechanical properties of Zr-1Nb at room and high temperature10.1016/j.jnucmat.2015.02.037 ↗
77. Size effects in indentation measurements of Zr-1Nb-0.05Cu alloy10.1016/j.msea.2015.01.024 ↗
78. Investigation of elevated-temperature mechanical properties of δ-hydride precipitate in Zircaloy-4 fuel cladding tubes using nanoindentation10.1016/j.jallcom.2017.07.321 ↗
79. Temperature-dependent hardening of zirconium alloys under heavy ion-irradiation: experimental observation and theoretical analysis10.1016/j.jnucmat.2022.153989 ↗