Formation of nanostructures in Ti2AlC induced by high-temperature helium irradiation

Su, Ranran; Zhang, Hongliang; Shi, Liqun; Wen, Haiming

doi:10.1016/j.jeurceramsoc.2019.01.056

Cited by 22 publications

(13 citation statements)

References 53 publications

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“…This irradiation-induced phase transformation from hcp-Mn+1AXn to fcc-(Mn+1A)Xn has been confirmed with He and Au irradiations performed on Ti3AlC2, Ti2AlC, Ti3SiC2, Nb4AlC3, V2AlC, Ti4AlN3, and Ti2AlN MAX phases [31]. Cracks may form during RT irradiations due to lattice distortions, i.e., a contraction along the <a> axis and an expansion along the <c> axis, which are minimized during irradiation at elevated temperatures [9,15,18,30]. Cracks were reported to nucleate at string-like and plate-like He bubbles [9,30].…”

Section: Introductionmentioning

confidence: 55%

“…Experimental findings have already indicated overall trends in the He irradiation response of the MAX phases. At room temperature (RT), the formation of spherical He bubbles has been reported [9,11,12,18,21,25,30]. In some studies, linear arrangements of spherical He bubbles seen in projection have been observed [9,30]; such defects are hereafter referred to as "stringlike" He bubbles, for brevity and consistency with the existing literature.…”

Section: Introductionmentioning

confidence: 80%

“…The MAX phases are steadily gaining attention for select envisaged nuclear applications, and a number of He irradiation studies on the MAX phases have already been reported in the open literature -for example on Ti3AlC2 [5,[9][10][11][12][13][14][15][16], Ti2AlC [17][18][19], Ti3SiC2 [6,[20][21][22], Cr2AlC [23,24], V2AlC [25], and Ti4AlN3 [19]. Overall, the He irradiation of MAX phase compounds tends to result in He atoms residing preferentially in the A-layer, thereby dislocating A-elements from their original sites [6,10,12,13,18,20,21]. First-principles calculations for both Ti3SiC2 and Ti3AlC2 suggested that the A-layers are the preferred sites for He atoms to reside [6,10,13,17].…”

Section: Introductionmentioning

confidence: 99%

“…Cracks were reported to nucleate at string-like and plate-like He bubbles [9,30]. Upon irradiation above 300 °C, the He bubbles tend to acquire plate-like shapes [9,18,21]. Irradiations at higher temperatures result in less damage, due to the dynamic recovery of defects.…”

Section: Introductionmentioning

confidence: 99%

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In situ He+ irradiation of the double solid solution (Ti0.5,Zr0.5)2(Al0.5,Sn0.5)C MAX phase: Defect evolution in the 350–800 °C temperature range

et al. 2021

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Thin foils of the double solid solution (Zr0.5,Ti0.5)2(Al0.5,Sn0.5)C MAX phase were in situ irradiated in a transmission electron microscope (TEM) up to a fluence of 1.310 17 ionscm -2 (7.5 dpa), using 6 keV He + ions. Irradiations were performed in the 350-800 °C temperature range. In situ and post-irradiation examination (PIE) by TEM was used to study the evolution of irradiationinduced defects as function of dose and temperature. Spherical He bubbles and string-like arrangements thereof, He platelets, and dislocation loops were observed. Dislocation loop segments were found to lie in non-basal-planes. At irradiation temperatures ≥ 450 °C, grain boundary tearing was observed locally due to He bubble segregation. However, the tears did not result in transgranular crack propagation. The intensity of specific spots in the selected area electron diffraction patterns weakened upon irradiation at 450 and 500 °C, indicating an increased crystal symmetry. Above 700 °C this was not observed, indicating damage recovery at the high end of the investigated temperature range. High-resolution scanning TEM imaging performed during the PIE of foils previously irradiated at 700 °C showed that the chemical ordering and nanolamination of the MAX phase were preserved after 7.5 dpa He + irradiation. The size distributions of the He platelets and spherical bubbles were evaluated as function of temperature and dose.

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Section: Introductionmentioning

confidence: 55%

Section: Introductionmentioning

confidence: 80%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

In situ He+ irradiation of the double solid solution (Ti0.5,Zr0.5)2(Al0.5,Sn0.5)C MAX phase: Defect evolution in the 350–800 °C temperature range

et al. 2021

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“…Although Ti 3 SiC 2 does not amorphize up to a very high radiation dose, it has been shown to undergo radiation-induced phase transformation, which can lead to deterioration of mechanical properties and microstructure stability. Phase transformation in these materials has been argued to be driven by chemical compositional changes ( 30 ) and/or by the formation and accumulation of defects ( 31 , 32 ). As TiC is naturally substoichiometric and C poor (i.e., has a large number of C vacancies) ( 33 ), the existence of TiC can affect the defect behaviors and chemical composition in Ti 3 SiC 2 , especially in the near-interface regions.…”

Section: Introductionmentioning

confidence: 99%

Enhancing the phase stability of ceramics under radiation via multilayer engineering

Zhang

et al. 2021

Sci. Adv.

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In metallic systems, increasing the density of interfaces has been shown to be a promising strategy for annealing defects introduced during irradiation. The role of interfaces during irradiation of ceramics is more unclear because of the complex defect energy landscape that exists in these materials. Here, we report the effects of interfaces on radiation-induced phase transformation and chemical composition changes in SiC-Ti3SiC2-TiCx multilayer materials based on combined transmission electron microscopy (TEM) analysis and first-principles calculations. We found that the undesirable phase transformation of Ti3SiC2 is substantially enhanced near the SiC/Ti3SiC2 interface, and it is suppressed near the Ti3SiC2/TiC interface. The results have been explained by ab initio calculations of trends in defect segregation to the above interfaces. Our finding suggests that the phase stability of Ti3SiC2 under irradiation can be improved by adding TiCx, and it demonstrates that, in ceramics, interfaces are not necessarily beneficial to radiation resistance.

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Defect behavior and radiation tolerance of MAB phases (MoAlB and Fe2AlB2) with comparison to MAX phases

Zhang

Kim

et al. 2020

Acta Materialia

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MAB phases are a new class of layered ternary materials that have already shown a number of outstanding properties. Here, we investigate defect evolution and radiation tolerance of two MAB phases, MoAlB and Fe2AlB2, using a combination of experimental characterization and firstprinciples calculations. We find that Fe2AlB2 is more tolerant to radiation-induced amorphization than MoAlB, both at 150 °C and at 300 °C. The results can be explained by the fact that the Mo Frenkel pair is unstable in MoAlB and as a result, irradiated MoAlB is expected to have a significant concentration of MoAl antisites, which are difficult to anneal even at 300 °C. We find that the tolerance to radiation-induced amorphization of MAB phases is lower than in MAX phases, but it is comparable to that of SiC. However, MAB phases do not show radiation-induced cracking which is observed in MAX phases under the same irradiation conditions. This study suggests that MAB phases might be a promising class of materials for applications that involve radiation.

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Formation of nanostructures in Ti2AlC induced by high-temperature helium irradiation

Cited by 22 publications

References 53 publications

In situ He+ irradiation of the double solid solution (Ti0.5,Zr0.5)2(Al0.5,Sn0.5)C MAX phase: Defect evolution in the 350–800 °C temperature range

In situ He+ irradiation of the double solid solution (Ti0.5,Zr0.5)2(Al0.5,Sn0.5)C MAX phase: Defect evolution in the 350–800 °C temperature range

Enhancing the phase stability of ceramics under radiation via multilayer engineering

Defect behavior and radiation tolerance of MAB phases (MoAlB and Fe2AlB2) with comparison to MAX phases

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