Heavy ion irradiation damage in Zr2AlC MAX phase

Qarra, H.H.; Knowles, Kevin M.; Vickers, M. E.; Akhmadaliev, S.; Lambrinou, Konstantina

doi:10.1016/j.jnucmat.2019.05.034

Cited by 23 publications

(9 citation statements)

References 30 publications

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“…Cracks parallel to the (0001) basal planes of the MAX phase appear on some grains in Fig. 4; these are characteristic of MAX phase materials; they are also observed in pristine Zr 2 AlC MAX phase [28] and the pristine Zr 3 AlC 2 MAX phase produced by Bowden et al for their irradiation work [29] . Post-irradiation examination of all the irradiated materials revealed no topographical discrepancies relative to the pristine sample, indicating that the ion irradiation did not alter the topography of the phases noticeably at a micrometre level.…”

Section: Microstructurementioning

confidence: 77%

“…Prior to the work reported here, there have been two studies, one on Zr 2 AlC [28] and one on Zr 3 AlC 2 and (Zr 0.5 Ti 0.5 ) 3 AlC 2 [29]. In the first of these two studies, Zr 2 AlC irradiated with Au 7+ ions was shown to develop significant lattice disorder and partial amorphisation upon irradiation to 3.5 dpa at RT conditions, whereas at 300 °C and 600 °C it exhibited relatively good irradiation resistance [28]. The second study used protons as their source of radiation, with irradiation temperatures of 350 °C and 575 °C [28].…”

Section: Introductionmentioning

confidence: 99%

“…In the first of these two studies, Zr 2 AlC irradiated with Au 7+ ions was shown to develop significant lattice disorder and partial amorphisation upon irradiation to 3.5 dpa at RT conditions, whereas at 300 °C and 600 °C it exhibited relatively good irradiation resistance [28]. The second study used protons as their source of radiation, with irradiation temperatures of 350 °C and 575 °C [28]. In this second study, c-parameter expansion and a-parameter contraction were reported in the irradiated samples, reducing as the temperature of irradiation increased, just as in the Ti-MAX phases, with Zr 3 AlC 2 shown to be able to exhibit dynamic defect recovery above 400 °C.…”

Section: Introductionmentioning

confidence: 99%

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Heavy ion irradiation damage in Zr3(Al0.9Si0.1)C2 MAX phase

Qarra

Knowles

Vickers

et al. 2020

Journal of Nuclear Materials

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A Zr 3 (Al 0.9 Si 0.1 )C 2 MAX phase-based ceramic with 22% wt. ZrC and 10% wt. Zr 5 Si 3 has been irradiated with 52 MeV I 9+ ions at room temperature, achieving a maximum dose of 8 displacements per atom (dpa). The response of this MAX phase-rich material to irradiation has been studied using scanning electron microscopy, transmission electron microscopy and X-ray diffraction techniques. Post-irradiation examination of the material revealed a number of crystalline changes to the MAX phase. At low doses, Zr 3 (Al 0.9 Si 0.1 )C 2 maintained a high degree of crystallinity, while at the highest doses, its degree of crystallinity was reduced significantly. A number of radiation-induced phase transformations were observed, including the decomposition of Zr 3 (Al 0.9 Si 0.1 )C 2 into ZrC and other phases, and the formation of -Zr 3 (Al,Si)C 2 , a MAX phase with a rearranged stacking sequence. Microstructural examination revealed that the majority of the extended defects in Zr 3 (Al 0.9 Si 0.1 )C 2 lie in the (0001) basal planes. Analysis of X-ray diffraction profiles after heat treating the 8 dpairradiated material for one hour at 300°C and at 600°C showed that there were only subtle changes to the profiles relative to that of the 8 dpa-irradiated material which had not been heat treated. Overall, the experimental results of this study show that the Zr 3 (Al 0.9 Si 0.1 )C 2 MAX phase responds less well to irradiation relative to other MAX phases irradiated with high energy heavy ions at room temperature.

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Section: Microstructurementioning

confidence: 77%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Heavy ion irradiation damage in Zr3(Al0.9Si0.1)C2 MAX phase

Qarra

Knowles

Vickers

et al. 2020

Journal of Nuclear Materials

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“…Zr is neutron transparent because its thermal neutron absorption cross -section is relatively tiny (Zr atoms have a small cross section for thermal neutrons), which can help nuclear reactors maintain a high neutron economy. As a result, it is routinely utilized in today's nuclear reactors [54]. Aside from economic reasons, Next-generation (Gen-III+) light water reactors (LWRs) require fuel cladding materials that can survive difficult operating circumstances such high mechanical and thermal loads, large neutron irradiation doses, and intensely oxid izing or corrosive environments [39].…”

Section: Future Perspective With Applications Of Zr 2 Ac Max Phasementioning

confidence: 99%

Overview in Technical Synthesis and Applications of Zr2AC (A= In, Sn, Pb, Al, S and Se) MAX phases: a brief review

HUSSEIN¹,

Abbas²,

Al-Ghaban³

2023

ETJ

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 The bulk Zr2AC ceramic M AX phase can be produced by hot isostatic pressing sintering, hot press sintering, and pressureless sintering.  At the higher temperatures, the M AX phase decomposes into M C and intermetallic compounds.  The most interesting Zr2AC M AX phase in nuclear applications.  Providing insight, the potential research prospects for this Zr2AC M AX phases in numerous fields.Zr2AC M AX phases are ternary carbide family with layered structures combining of the outstanding characteristics of metals and ceramics. This review study provides an overview of Zr2AC M AX phase formation mechanisms, applications, and the correlation between Zr2AC M AX phase formation mechanisms and performance in applications such solar coatings, oxidation resistance, high temperature applications, and nuclear applications. Zr2InC M AX phase has low friction and wear materials that can be used for variety applications for significant technology such as electrical spinning connections and rotating bearings. M ore examples, the Zr2SnC M AX phase uses for self-healing of cracks and oxidation resistance. The Zr2PbC M AX phases are elastic and electrically anisotropic in nature and appropriate for high temperature applications, optoelectronic devices, and coating materials. Studying the optical characteristics of the Zr2SeC has shown its potential for application as a shielding material in order to decrease the heating of solar. The Zr2SC is suitable for use in high-temperature technologies, such as thermal barrier coating material TBC. The Zr2AlC phase is the most attractive among all non-synthesizable ternary M AX phases, particularly for the nuclear industry. There are a lot of challenges during fabrication of the M AX phase, including synthesis temperature, the M AX phase purity, and the secondary phase (impurities). In harsh external conditions, the defect density has a substantial impact on the M AX phase's stability and thus, the methods of defect formation and migration have a considerable impact on the phases' radiation resistance and selfhealing capabilities.

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“…In recent years, there has been a search for different applications for the use of this family of materials. Their use as heat exchangers [7] or catalytic devices using porous Ti 3 SiC 2 and Ti 2 AlC [8], thermal barriers using Cr 2 AlC [9] or as fuel cladding material in nuclear reactors using Zr 2 AlC [10] are some of the possible applications of these materials.…”

Section: Introductionmentioning

confidence: 99%

Sinterability, Mechanical Properties and Wear Behavior of Ti3SiC2 and Cr2AlC MAX Phases

et al. 2022

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MAX phases are a promising family of materials for several demanding, high-temperature applications and severe conditions. Their combination of metallic and ceramic properties makes MAX phases great candidates to be applied in energy production processes, such as high temperature heat exchangers for catalytic devices. For their successful application, however, the effect of the processing method on properties such as wear and mechanical behavior needs to be further established. In this work, the mechanical and wear properties of self-synthesized Ti3SiC2 and Cr2AlC MAX phase powders consolidated by different powder metallurgy routes are evaluated. Uniaxial pressing and sintering, cold isostatic pressing and sintering and hot pressing were explored as processing routes, and samples were characterized by analyzing microstructure, phase constitution and porosity. Wear behavior was studied by reciprocating-sliding tests, evaluating the wear rate by the loss of material and the wear mechanism.

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Heavy ion irradiation damage in Zr2AlC MAX phase

Cited by 23 publications

References 30 publications

Heavy ion irradiation damage in Zr3(Al0.9Si0.1)C2 MAX phase

Heavy ion irradiation damage in Zr3(Al0.9Si0.1)C2 MAX phase

Overview in Technical Synthesis and Applications of Zr2AC (A= In, Sn, Pb, Al, S and Se) MAX phases: a brief review

Sinterability, Mechanical Properties and Wear Behavior of Ti3SiC2 and Cr2AlC MAX Phases

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