Effects of helium ion irradiation on the high temperature oxidation resistance of Inconel 718 alloy

Wei, Haiqing; Ding, Zhan; Wang, Jian; Yin, Yajun; Guo, Qinhan; Gong, Yuling; Zhao, Zhenjiang; Yao, Xiuyuan

doi:10.1016/j.surfcoat.2019.02.021

Cited by 9 publications

(4 citation statements)

References 33 publications

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“…Alloy 230 has been shown to form chromium oxide layers on the surface at 950 • C [11,12] and aluminum oxide internally [11]. A comparison of the corrosion rates between irradiated and non-irradiated Inconel 718 at 900 • C shows that irradiation accelerates the growth of a denser scale of Cr 2 O 3 as well as the inner oxide layers of Al 2 O 3 and TiO 2 , and improves the material's resistance to oxidation [13]. Inconel 617's creep behavior was investigated in air and helium environments at high temperatures.…”

Section: Introductionmentioning

confidence: 99%

The Influence of High-Temperature Helium and the Amount of Revert Material on the Material Properties of Inconel 738

et al. 2022

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Nickel-based alloys are considered promising materials for primary circuits of high-temperature gas reactors (HTGRs), specifically for gas turbines. The primary helium (He) coolant in the gas-turbine-based HTGRs is expected to reach temperatures of up to 900 °C; therefore, the selected materials should adequately perform over a long service life at such an environment. A promising manufacturing method in the production of reactor components is precision casting, where the content of revert (recyclate) material in the alloy differs and can influence the material behavior. In our study, Inconel alloy 738 was manufactured by casting 50% and 100% of revert material and tested in HTGR conditions to examine the influence of helium coolant on the material’s properties. Tensile specimens were exposed at 900 °C for 1000 h in helium containing a specified amount of gaseous impurities. Scanning electron microscopy (SEM) with energy dispersive spectroscopy (EDS), in combination with X-ray diffraction (XRD) and nano-, microhardness methods, were used for material characterization after performing the tensile tests at room temperature. The presence of three types of layers was observed: a thin layer formed by aluminum and chromium oxides on the surface; non-uniform surface oxides Ti3O5 with inner (Al,Cr)2O3; and the inner fine-grained Inconel Cr-enriched phase (approx. 10–20 µm below the surface), which can act as a protective surface layer. Mechanical properties of both revert materials decreased after exposure to HTGR conditions but did not show a significant difference as a result of the content of the revert material. The increase of nano-hardness in line profiles throughout the specimen’s cross-section was observed locally at the surface oxides and in the precipitates and grain boundaries. After exposure, Rp0.2 values decreased by 20% and 17.7%, and Rm values by 12.3% and 20.8% in samples with 50 and 100% revert content, respectively. Furthermore, a decrease in microhardness values (HV0.1) was detected by 4.98% in longitude and 5.80% in cross-section for samples with 50% revert material and by 3.85% in longitude and 7.86% in cross-section for samples with 100% revert material. It can be concluded that both revert materials have similar corrosion resistance in HTGR conditions. The presented results complement the knowledge about the degradation of alloys in the coolant environment of advanced gas-cooled reactors.

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Section: Introductionmentioning

confidence: 99%

The Influence of High-Temperature Helium and the Amount of Revert Material on the Material Properties of Inconel 738

et al. 2022

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“…[16] The helium defect diffuses to the surface in the form of interstitial atoms and releases on the surface. [17,18] Therefore, thermal desorption spectropy (TDS) can analyze helium bubbles with small size, and each characteristic peak may represent a different desorption process. [19,20] Supplementary to conventional mechanical measurements, now it is the simplest, most practical, and indirect method to study the behavior of helium and their defects (a single atom, and bubbles).…”

Section: Introductionmentioning

confidence: 99%

Thermal desorption characteristic of helium ion irradiated nickel-base alloy*

Zhu

Zhao

et al. 2020

Chinese Phys. B

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The nickel-base alloy is one of the leading candidate materials for generation IV nuclear reactor pressure vessel. To evaluate its stability of helium damage and retention, helium ions with different energy of 80 keV and 180 keV were introduced by ion implantation to a certain dose (peak displacement damage 1–10 dpa). Then thermal desorption spectroscopy (TDS) of helium atoms was performed to discuss the helium desorption characteristic and trapping sites. The desorption peaks shift to a lower temperature with increasing dpa for both 80 keV and 180 keV irradiation, reflecting the reduced diffusion activation energy and faster diffusion within the alloy. The main release peak temperature of 180 keV helium injection is relatively higher than that of 80 keV at the same influence, which is because the irradiation damage of 180 keV, helium formation and entrapment occur deeper. The broadening of the spectra corresponds to different helium trapping sites (He–vacancies, grain boundary) and desorption mechanisms (different He n V m size). The helium retention amount of 80 keV is lower than that of 180 keV, and a saturation limit associated with the irradiation of 80 keV has been reached. The relatively low helium retention proves the better resistance to helium bubbles formation and helium brittleness.

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“…In samples with ion irradiation, it has been known that defects such as dislocations, dislocation loops, SFTs and cavities produced by ion irradiation would alter the performance of an irradiated layer [13][14][15]. As a commonly used fuel cladding material in a low-temperature reactor, studying the influence of irradiation on microstructure is also beneficial to understand the stress status in the irradiated layer.…”

Section: Introductionmentioning

confidence: 99%

The Formation of Microcrystal in Helium Ion Irradiated Aluminum Alloy

et al. 2019

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A microstructure variation in Al-1060 alloy after helium ion irradiation was revealed by a transmission electron microscope (TEM). The result shows that ion irradiation produced dislocations, dislocation loops, cavities and microcrystals in the irradiated layer. Dislocation-defect interactions were portrayed, especially the pinning effect of a dislocation loop and cavity on moving dislocation. Irradiation-induced stress was recognized as the main factor which impacted on the interaction of defect. Based on the dislocation inhibited with irradiation defects, the mechanism of microcrystal formation was proposed.

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Effects of helium ion irradiation on the high temperature oxidation resistance of Inconel 718 alloy

Cited by 9 publications

References 33 publications

The Influence of High-Temperature Helium and the Amount of Revert Material on the Material Properties of Inconel 738

The Influence of High-Temperature Helium and the Amount of Revert Material on the Material Properties of Inconel 738

Thermal desorption characteristic of helium ion irradiated nickel-base alloy*

The Formation of Microcrystal in Helium Ion Irradiated Aluminum Alloy

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