Cr-coated Zr-4 alloy prepared by electroplating and its in situ He+ irradiation behavior
Source abstract
Abstract
Abstract With the aim of improving the oxidation resistance of zirconium alloy claddings in light water reactors and enhancing the deposition efficiency and economics of surface coating, electroplating was used to deposit a Cr coating with a rate exceeding 12 μm/h on the surface of thermally treated Zr-4 alloy predeposited with an intermediate transition nickel layer. The evolution of helium bubbles in the cross-section of the Cr-coated Zr-4 alloy during 30 keV He+ irradiation at 400 °C was in situ analyzed at a newly constructed facility named the Xiamen Multiple Ion Beam In situ Analysis TEM Facility, which is the only running in situ irradiation facility at China. The thermal treatment induced chemical reactions between nickel and zirconium to form a multilayer structure (Ni5Zr, Ni7Zr2, Ni3Zr, Ni10Zr7, NiZr and NiZr2 in sequence) with metallurgical bonding. Meanwhile, the Cr coating combined with the Ni layer in a lattice-matching mode. No defects could be found at the interface between each layer. The different phases and interfaces showed different resistance abilities towards He+ irradiation, where the size and distribution characteristics of bubbles were different. A bubble-free zone could be observed adjacent to the interface between Cr and Ni layers; however, bubbles mainly aggregated at the interface between Ni and Ni5Zr layers. With the increase in helium concentration, both the size and density of bubbles increased in the Cr coating. Helium atoms precipitated preferentially along Cr grain boundaries to form bubbles and then further gathered to form short bubble microcracks. The results were discussed in terms of the energetics of the material system and the surface diffusion mechanism.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (68)
Show source-provided references
1. Accident tolerant fuel cladding development: promise, status, and challenges10.1016/j.jnucmat.2017.12.043 ↗
2. Current status of materials development of nuclear fuel cladding tubes for light water reactors10.1016/j.nucengdes.2017.02.031 ↗
3. Accident tolerant fuels for LWRs: a perspective10.1016/j.jnucmat.2013.12.005 ↗
4. Development status of accident tolerant fuel for light water reactors in Korea10.1016/j.net.2015.11.011 ↗
5. Overview of the US DOE accident tolerant fuel development program
6. Multiscale characterization of irradiation behaviour of ion-irradiated SiC/SiC composites10.1016/j.actamat.2018.09.012 ↗
7. Linking microstructure and local mechanical properties in SiC-SiC fiber composite using micromechanical testing10.1016/j.actamat.2019.02.001 ↗
8. Effects of Laves phase particles on recovery and recrystallization behaviors of Nb-containing FeCrAl alloys10.1016/j.actamat.2017.11.027 ↗
9. Dislocation loop evolution during in-situ ion FeCrAl alloys10.1016/j.actamat.2017.07.011 ↗
10. Interface stability, mechanical and corrosion properties of AlCrMoNbZr/(AlCrMoNbZr)N high-entropy alloy multilayer coatings under helium ion irradiation10.1016/j.apsusc.2019.04.192 ↗
11. Microstructure analysis of Kr+ irradiation and post-irradiation corrosion of modified N36 zirconium alloy10.1016/j.nimb.2017.04.066 ↗
12. High-intensity low energy titanium ion implantation into zirconium alloy10.1016/j.apsusc.2018.01.021 ↗
13. In-situ TEM observation of growth behavior of Kr bubbles in Zirconium alloy during post-implantation annealing10.1016/j.nimb.2012.11.085 ↗
14. Surface microstructures and high-temperature high-pressure corrosion behavior of N18 zirconium alloy induced by high current pulsed electron beam irradiation10.1016/j.apsusc.2019.04.124 ↗
15. Early studies on Cr-Coated Zircaloy-4 as enhanced accident tolerant nuclear fuel claddings for light water reactors10.1016/j.jnucmat.2019.02.018 ↗
16. Influence of plasma immersion titanium implantation on hydrogenation and mechanical properties of Zr-2.5Nb10.1016/j.apsusc.2016.02.149 ↗
17. Surface treatment to form a dispersed Y2O3 layer on Zircaloy-4 tubes10.1016/j.apsusc.2017.06.108 ↗
18. Degradation and structure evolution in corrosive LiOH solution of microarc oxidation coated Zircaloy-4 alloy in silicate and phosphate electrolytes10.1016/j.apsusc.2017.04.226 ↗
19. Effects of ion irradiation on chromium coatings of various thicknesses on a zirconium alloy10.1016/j.jnucmat.2019.151740 ↗
20. High-temperature oxidation of thick Cr coating prepared by arc deposition for accident tolerant fuel claddings10.1016/j.jnucmat.2019.01.039 ↗
21. Behavior under LOCA conditions of enhanced accident tolerant chromium coated zircaloy-4 claddings
22. Microstructure and oxidation behavior of CrAl laser-coated Zircaloy-4 alloy10.3390/met7020059 ↗
23. Nickel-chromium (Ni–Cr) coatings deposited by magnetron sputtering for accident tolerant nuclear fuel claddings10.1016/j.surfcoat.2019.04.057 ↗
24. Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO™10.1016/j.jnucmat.2018.05.014 ↗
25. High temperature steam oxidation of Al3Ti-based alloys for the oxidation-resistant surface layer on Zr fuel claddings10.1016/j.jnucmat.2013.01.338 ↗
26. Preparation, structure, and properties of an AlCrMoNbZr high-entropy alloy coating for accident-tolerant fuel cladding10.1016/j.surfcoat.2018.04.037 ↗
27. Characterization of Al2O3/ZrO2 composite coatings deposited on Zr-2.5Nb alloy by plasma electrolytic oxidation10.1016/j.apsusc.2018.04.207 ↗
28. Improved oxidation resistance of zirconium at high-temperature steam by magnetron sputtered Cr-Al-Si ternary coatings10.1016/j.surfcoat.2018.04.029 ↗
29. SiC/Si thin film deposited on zircaloy to improved accident tolerant fuel cladding10.1016/j.tsf.2018.06.006 ↗
30. Comparison of the oxidation behavior of a zirconium nitride coating in water vapor and air at high temperature10.1016/j.corsci.2018.04.015 ↗
31. Influence of Zr alloying on the mechanical properties, thermal stability and oxidation resistance of Cr-Al-N coatings10.1016/j.apsusc.2014.08.115 ↗
32. Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding10.1016/j.jnucmat.2015.06.028 ↗
33. Roberts · 2016
34. Evaluation of corrosion and oxidation behaviors of TiAlCrN coatings for nuclear fuel cladding10.1016/j.surfcoat.2018.11.083 ↗
35. Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding10.1016/j.jnucmat.2016.05.021 ↗
36. Mechanical analysis of surface-coated zircaloy cladding10.1016/j.net.2017.03.012 ↗
37. Neutronic evaluation of coating and cladding materials for accident tolerant fuels10.1016/j.pnucene.2015.11.006 ↗
38. Protection of zirconium by alumina- and chromia-forming iron alloys under high-temperature steam exposure10.1016/j.jnucmat.2013.03.006 ↗
39. Characterization of the hydrothermal corrosion behavior of ceramics for accident tolerant fuel cladding
40. Oxidation of advanced zirconium cladding alloys in steam at temperatures in the range of 600-1200°C10.1007/s11085-011-9249-3 ↗
41. Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures10.1016/j.jnucmat.2009.04.018 ↗
42. Material Selection for accident tolerant fuel cladding
43. HRTEM and chemical study of an ion-irradiated chromium/Zircaloy-4 interface10.1016/j.jnucmat.2018.01.029 ↗
44. AREVA NP’s enhanced accident-tolerant fuel developments: focus on Cr-coated M5 cladding10.1016/j.net.2017.12.004 ↗
45. Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-ofcoolant accident conditions10.1016/j.jnucmat.2016.10.021 ↗
46. Designing radiation resistance in materials for fusion energy10.1146/annurev-matsci-070813-113627 ↗
47. Adhesion property and high-temperature oxidation behavior of Cr-coated Zircaloy-4 cladding tube prepared by 3D laser coating10.1016/j.jnucmat.2015.06.030 ↗
48. High temperature steam-oxidation behavior of arc ion plated Cr coatings for accident tolerant fuel claddings10.1016/j.surfcoat.2015.09.022 ↗
49. Hydrogenation behavior of Ti-implanted Zr-1Nb alloy with TiN films deposited using filtered vacuum arc and magnetron sputtering10.1016/j.apsusc.2017.04.035 ↗
50. Behavior of plasma sprayed Cr coatings and FeCrAl coatings on Zr fuel cladding under loss-of-coolant accident conditions10.1016/j.surfcoat.2018.03.016 ↗
51. Development of Cr cold spray-coated fuel cladding with enhanced accident tolerance10.1016/j.net.2017.12.011 ↗
52. Development of cold spray coatings for accident-tolerant fuel cladding in light water reactors10.1007/s11837-017-2643-9 ↗
53. Shah · 2017
54. Vacuum-arc chromium-based coatings for protection of zirconium alloys from the high-temperature oxidation in air10.1016/j.jnucmat.2015.06.016 ↗
55. Powers · 1980
56. In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications10.1016/j.jnucmat.2018.10.023 ↗
57. Depth-controlled grazing-incidence diffraction of synchrotron x radiation10.1103/PhysRevLett.56.1144 ↗
58. Effect of alloying elements on defect evolution in Ni-20X binary alloys10.1016/j.actamat.2018.03.054 ↗
59. Helium accumulation in metals during irradiation – where do we stand?10.1016/j.jnucmat.2003.09.001 ↗
60. First-principles studies on structural, mechanical, thermodynamic and electronic properties of Ni–Zr intermetallic compounds10.1016/j.intermet.2014.05.021 ↗
61. Helium bubble behaviour in BCC metals below 0.65Tm
62. The stability of gas bubbles in an irradiation environment10.1016/0022-3115(69)90189-5 ↗
63. The solution of inert gas atoms in metals10.1080/14786435708243211 ↗
64. Inert gases in metals10.1179/imr.1966.11.1.159 ↗
65. Helium bubbles in nickel annealed at T>0.7Tm10.1016/S0022-3115(97)00275-4 ↗
66. Breakaway bubble growth during the annealing of helium bubbles in metals10.1016/j.jnucmat.2004.04.349 ↗
67. Bubble diffusion and the motion of point defects near surfaces10.1002/pssb.19670210202 ↗
68. Kinetics of diffusional motion of pores in solids10.1016/0022-3115(69)90176-7 ↗