journal article·2024-07

A novel nano-structured zirconium alloy prospective for high temperature applications

Huajian Wu, Yong Jiang, Jiacheng Shang, Yiren Wang, Fuhua Cao

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Abstract

Zirconium alloys have many advantages for structural applications in nuclear reactors, but their use has been generally restricted at temperatures below 400 °C. In this study, a novel nano-structured Zr alloy was successfully fabricated by ball milling and hot-isostatic-pressing, using Zr, Sn, ZrH 2 and nano-Y 2O 3 as raw powders. The alloy microstructure was characterized to be uniquely featured with a very fine grain structure (mean size: ∼3 μm) and a high number density of highly-coherent, ultra-fine nano-precipitates (mean size: 4.2 nm, density: ∼2.52×10 23 m −3). These nano-precipitates were identified as Y 2Zr 2O 7, with the interfacial orientation relation of 001 ( 010 ) Y 2 Zr 2 O 7 // 0001 2 1 ̅ 1 ̅ 0 Zr . This new alloy achieved remarkably-improved strength and heat resistance from room temperature up to 600 °C for at least 1000 h, which is superior to all the current commercial Zr alloys, especially to Zr-2 and Zr-4 alloys with a more comparable matrix composition.
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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 (77)

Show source-provided references
1. Overview of reactor systems and operational environments for structural materials in gen-IV fission reactors
2. Uses of zirconium alloys in fusion applications10.1016/S0022-3115(00)00146-X ↗
3. Review of blanket designs for advanced fusion reactors10.1016/j.fusengdes.2008.07.039 ↗
4. Stacking faults in Zr(Fe, Cr)2 Laves structured secondary phase particle in Zircaloy-4 alloy10.1039/C7NR08963E ↗
5. Analysis of atomic distribution in as-fabricated Zircaloy-2 claddings by atom probe tomography under high-energy pulsed laser10.1016/j.jnucmat.2013.08.048 ↗
6. Observation of c-component dislocation structures formed in pure Zr and Zr-base alloy by self-ion accelerator irradiation10.1016/j.jnucmat.2011.12.035 ↗
7. 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 ↗
8. The effect of Sn on autoclave corrosion performance and corrosion mechanisms in Zr–Sn–Nb alloys10.1016/j.actamat.2013.03.046 ↗
9. Correlation between microstructure and corrosion behavior of Zr–Nb binary alloy10.1016/S0022-3115(02)00703-1 ↗
10. Effect of Nb and Fe on damage evolution in a Zr-alloy during proton and neutron irradiation10.1016/j.actamat.2018.12.021 ↗
11. Effects of copper addition on the tensile properties and microstructures of modified Zircaloy-410.1016/S0022-3115(00)00014-3 ↗
12. Effect of molybdenum on properties of zirconium components of nuclear reactor core10.1016/j.nme.2018.01.001 ↗
13. Moiré fringes in nanoprecipitates in a zirconium alloy10.1016/j.matlet.2020.127678 ↗
14. An origin of corrosion resistance changes of Zr alloys: effects of Sn and Nb on grain boundary strength of surface oxide10.1016/j.actamat.2021.116804 ↗
15. Corrosion of zirconium alloys used for nuclear fuel cladding10.1146/annurev-matsci-070214-020951 ↗
16. Towards a better understanding of the oxide film growth mechanism in E110 zirconium alloy under high-temperature oxidation in steam10.1515/corrrev-2019-0094 ↗
17. EELS and atom probe tomography study of the evolution of the metal/oxide interface during zirconium alloy oxidation10.1016/j.jnucmat.2015.03.043 ↗
18. Microstructure and texture evolution during thermomechanical processing of β-quenched Zr10.1016/j.actamat.2014.12.033 ↗
19. Microstructural evolution in (α + βZr) region of Zr-2.5 wt% Nb annealed at different temperatures: Effect on mechanical properties10.1016/j.jnucmat.2019.151978 ↗
20. P.L. Rittenhouse, M.L. Picklesimer, Metallurgy of Zircaloy-2. PART I. The effects of fabrication variables on the anisotropy of mechanical properties, Office of Scientific & Technical Information Technical Reports (1960).10.2172/4108096 ↗
21. Mechanical properties and microstructure evolution during deformation of ultrafine grained zirconium at low temperatures
22. Mechanical behaviour and microstructural characterizations of ultrafine grained Zircaloy-2 processed by cryorolling10.1016/j.msea.2014.02.025 ↗
23. Structure and mechanical properties of a Zr-1Nb alloy, obtained by the method of severe plastic deformation10.1016/j.matpr.2015.04.033 ↗
24. An investigation of deformed microstructure and mechanical properties of Zircaloy-4 processed through multiaxial forging10.1016/j.matchemphys.2015.09.025 ↗
25. Study of precipitate evolution and recrystallization of β-quenched Zr–Sn–Nb–Fe–Cr–Cu alloy during aging10.1016/j.jnucmat.2012.05.009 ↗
26. Effect of predeformation on microstructural evolution of a Zr alloy during 550–700°C aging after β quenching10.1016/j.actamat.2013.02.001 ↗
27. High temperature zirconium alloys for fusion energy10.1016/j.jnucmat.2021.153431 ↗
28. On the potentiality of using ferritic/martensitic steels as structural materials for fusion reactors10.1088/0029-5515/44/1/006 ↗
29. On the role of alloy composition and processing parameters in nanocluster formation and dispersion strengthening in nanostuctured ferritic alloys10.1016/j.actamat.2008.09.025 ↗
30. Assessing the effects of radiation damage on Ni-base alloys for the prometheus space reactor system10.1016/j.jnucmat.2007.01.217 ↗
31. The fabrication of vanadium base alloys as candidate fusion reactor materials10.1016/0022-3115(88)90381-9 ↗
32. Silicon carbide composites as fusion power reactor structural materials10.1016/j.jnucmat.2011.03.005 ↗
33. Microstructural characterization of a new mechanically alloyed Ni-base ODS superalloy powder10.1016/j.matchar.2014.12.008 ↗
34. Microstructure control of Co-base ODS alloys10.4028/www.scientific.net/AMR.239-242.864 ↗
35. Microstructure, mechanical properties, and strengthening mechanisms of nanostructural Y-Zr-O oxide dispersion-strengthened (ODS) Mo alloys10.1016/j.jallcom.2022.166155 ↗
36. Microstructure development of Y–Ti–O dispersion strengthened Cu alloys fabricated by mechanical alloying10.1016/j.matchar.2022.111808 ↗
37. Achieving high strength and ductility in ODS-W alloy by employing oxide@W core-shell nanopowder as precursor10.1038/s41467-021-25283-2 ↗
38. Synergic strengthening by oxide and coherent precipitate dispersions in high-entropy alloy prepared by powder metallurgy10.1016/j.scriptamat.2018.07.034 ↗
39. Possible fast-reactor canning materials strengthened and stabilized by dispersion10.1179/pom.1967.10.20.010 ↗
40. Alloying design of oxide dispersion strengthened ferritic steel for long life FBRs core materials10.1016/0022-3115(93)90200-I ↗
41. Recent developments in irradiation-resistant steels10.1146/annurev.matsci.38.060407.130315 ↗
42. Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress10.1016/j.actamat.2007.09.016 ↗
43. Stability of a model Fe-14Cr nanostructured ferritic alloy after long-term thermal creep10.1016/j.scriptamat.2019.06.001 ↗
44. Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa10.1016/j.jnucmat.2014.06.011 ↗
45. The ferrite/oxide interface and helium management in nano-structured ferritic alloys from the first principles10.1016/j.actamat.2015.10.031 ↗
46. Radiation tolerance of complex oxides10.1126/science.289.5480.748 ↗
47. Radiation-induced amorphization resistance and radiation tolerance in structurally related oxides10.1038/nmat1842 ↗
48. On dispersion strengthening of zirconium
49. Dispersion-strengthened zirconium alloys10.1016/0022-5088(65)90055-X ↗
50. Structure and properties of yttria-zirconium dispersions10.1016/0022-3115(68)90102-5 ↗
51. Zirconium alloys dispersion strengthened with yttria10.1179/cmq.1972.11.1.223 ↗
52. Synthesis and characterization of nano-Y2O3 dispersed Zr-based alloys by mechanical alloying and conventional sintering
53. Development of nano-Y2O3 dispersed Zr alloys synthesized by mechanical alloying and consolidated by pulse plasma sintering10.1016/j.matchar.2017.12.038 ↗
54. Geometrically necessary dislocations and strain-gradient plasticity a few critical issues10.1016/S1359-6462(02)00335-4 ↗
55. Microstructure characterization of gradient structured surface layer in pure zirconium10.1016/j.matchar.2021.110924 ↗
56. Mechanical alloying and milling10.1016/S0079-6425(99)00010-9 ↗
57. Structural defects and thermal stability of Ti(Al) solid solution obtained by mechanical alloying10.1016/S0921-5093(97)00503-0 ↗
58. Prediction on phase stabilities of the Zr–H system from the first-principles10.1007/s40195-020-01113-0 ↗
59. Phase transformations during cooling from the βZr phase temperature domain in several hydrogen-enriched zirconium alloys studied by in situ and ex situ neutron diffraction10.1016/j.actamat.2020.08.061 ↗
60. Quantitative tests revealing hydrogen-enhanced dislocation motion in α-iron10.1038/s41563-023-01537-w ↗
61. Mechanical properties of zirconium alloys and zirconium hydrides predicted from density functional perturbation theory10.1039/C5DT03403E ↗
62. Mechanical alloying of brittle materials10.1007/BF02647712 ↗
63. Effects of β-cooling rates on microstructural characteristics and hardness variation of a dual-phase Zr alloy10.1016/j.ijrmhm.2021.105619 ↗
64. Diffraction contrast from spherically symmetrical coherency strains
65. Developing core-shell nano-structures in FeCrAl-ODS ferritic alloys with the Co-addition of Ni and Zr10.1007/s40195-023-01621-9 ↗
66. Pressure-induced structural transition of Y2Zr2O710.1016/j.jallcom.2015.11.137 ↗
67. Thermal equations of state of theα, β, and ω phases of zirconium10.1103/PhysRevB.71.184119 ↗
68. Fatigue behavior of Zircaloy-2 under asymmetric loading at 400°C10.1016/j.ijpvp.2017.11.012 ↗
69. Examination of the plastic properties of Zircaloy-4 at elevated temperatures in air atmosphere10.1016/0022-3115(76)90281-6 ↗
70. High temperature mechanical behavior of Zr–2.5% Nb alloy10.1016/j.nucengdes.2005.05.032 ↗
71. Effects of hydride precipitation on the mechanical property of cold worked zirconium alloys in fully recrystallized condition10.1016/j.net.2019.07.032 ↗
72. Microstructure and mechanical properties of large-scale ingots of the Zr-1Mo alloy10.2320/matertrans.M2015098 ↗
73. New low-Sn Zr cladding alloys with excellent autoclave corrosion resistance and high strength10.3390/met7040144 ↗
74. Optimization of phase composition and mechanical properties in Zr alloys by micro-alloying10.1016/j.matlet.2017.05.082 ↗
75. A novel Zr-based alloy microstructure with high strength and excellent ductility10.1016/j.msea.2015.10.106 ↗
76. Microstructure and mechanical properties of ZrBe alloys processed by hot rolling10.1016/j.msea.2016.05.017 ↗
77. Studies on hot hardness of Zr and its alloys for nuclear reactors10.1016/S0022-3115(98)00610-2 ↗