Irradiation resistance of MAX phases Ti3SiC2 and Ti3AlC2: Characterization and comparison

Huang, Qing; Liu, Renduo; Lei, Guanhong; Huang, Hefei; Jianjian, Li; He, Songnian; Li, Dehui; Liu, Yan; Zhou, Jie

doi:10.1016/j.jnucmat.2015.06.056

Cited by 51 publications

(43 citation statements)

References 18 publications

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“…Irradiation induced decomposition of MAX phase to an MX crystal structure is noted in literature. [10,12,35,39,40] and 600 °C (Haung et al). [10,12,16,35,39,40] This is because point-defect swelling is also mitigated above ~500°C and is not observed in neutron irradiations above ~700°C.…”

Section: Intragranular Tic (M-x)mentioning

confidence: 99%

“…[10,12,35,39,40] and 600 °C (Haung et al). [10,12,16,35,39,40] This is because point-defect swelling is also mitigated above ~500°C and is not observed in neutron irradiations above ~700°C. [16] Furthermore, TiC (1-x) phase fitted to the Rietveld solution after irradiation at ~400°C has an improbable crystallite size because TEM of TiC (1-x) irradiated at 0.1 dpa showed "black spot" radiation damage (exceeding the authors' ability to count [10,15]).…”

Section: Intragranular Tic (M-x)mentioning

confidence: 99%

“…[11] For Ti 3 AlC 2 anisotropic LP expansion is 50% higher at room temperature ion irradiations and neutron irradiations at 400°C, and a-axis shrinkage is also observed. [10,[12][13][14] Mechanical properties are highly influenced by defect induced swelling. Ti 3 AlC 2 and Ti 2 AlC after neutron irradiation at ~400°C at 2 dpa and 0.1 dpa respectively report microcracking, and irradiated Ti 3 AlC 2 -Ti 5 Al 2 C 3 reported low fracture strengths of ~30 MPa.…”

Section: Introductionmentioning

confidence: 99%

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Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C

Ang

Parish

Shih

et al. 2017

Journal of the European Ceramic Society

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The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan). This work reports the first mechanical properties of Ti 3 AlC 2-Ti 5 Al 2 C 3 materials neutron irradiated at ~400, 630 and 700°C at a fluence of 2 x 10 25 n. m-2 (E > 0.1 MeV or a displacement dose of ~ 2 dpa. After irradiation at ~400°C, anisotropic swelling and loss of 90% flexural strength was observed. After irradiation at ~630-700°C, properties were unchanged. Microcracking and kinking-delamination had occurred during irradiation at ~630-700°C. Further examination showed no cavities in Ti 3 AlC 2 after irradiation at ~630°C, and lamellar of MX 6 and A were preserved. However, disturbance of (0004) reflections corresponding to M-A layers was observed, and the number density of line/planar defects was ~10 23 m-3 of size 5-10 nm. HAADF identified these defects as antisite Ti Al atoms. Ti 3 AlC 2-Ti 5 Al 2 C 3 shows abrupt dynamic recovery of A-layers from ~630°C, but a higher temperature appears necessary for full recovery. high fracture toughness values (of up 10 MPa. m ½ (compared to values of ~4 MPa. m ½ in monolithic SiC, for example)[2] are the result of dislocation-based kink bands that delaminate from the M-A layers within grains, coupled with diffuse intragranular microcracking, high-aspect ratio grain interlocking and push/pull-out mechanisms.[3-5] The key properties of interest for

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Section: Intragranular Tic (M-x)mentioning

confidence: 99%

Section: Intragranular Tic (M-x)mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C

Ang

Parish

Shih

et al. 2017

Journal of the European Ceramic Society

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“…A large number of experimental studies [11,12,13,14,24,25,26,27,28,29,30,31] have investigated the properties of Ti 3 SiC 2 and Ti 3 AlC 2 when subjected to irradiation with heavy ions and neutrons. Nappé et al [11] studied the defect properties of Ti 3 SiC 2 under Au-, Kr-, and Xe-ion irradiation.…”

Section: Introductionmentioning

confidence: 99%

First-Principles Study of Vacancies in Ti3SiC2 and Ti3AlC2

et al. 2017

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MAX phase materials have attracted increased attention due to their unique combination of ceramic and metallic properties. In this study, the properties of vacancies in Ti3AlC2 and Ti3SiC2, which are two of the most widely studied MAX phases, were investigated using first-principles calculations. Our calculations indicate that the stabilities of vacancies in Ti3SiC2 and Ti3AlC2 differ greatly from those previously reported for Cr2AlC. The order of the formation energies of vacancies is VTi(a) > VTi(b) > VC > VA for both Ti3SiC2 and Ti3AlC2. Although the diffusion barriers for Ti3SiC2 and Ti3AlC2 are similar (~0.95 eV), the properties of their vacancies are significantly different. Our results show that the vacancy–vacancy interaction is attractive in Ti3AlC2 but repulsive in Ti3SiC2. The introduction of VTi and VC vacancies results in the lattice constant c along the [0001] direction increasing for both Ti3SiC2 and Ti3AlC2. In contrast, the lattice constant c decreases significantly when VA are introduced. The different effect of VA on the lattice constants is explained by enhanced interactions of nearby Ti layers.

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“…Usually, the irradiation-induced c -parameter expansion in MAX phases is accompanied by an a -parameter contraction [5,7,18,21,24,26,[41][42][43] . Fig.…”

Section: Xrd Study Of Proton-irradiated Materialsmentioning

confidence: 99%

The Stability of Irradiation-Induced Defects in Zr 3AlC 2, Nb 4AlC 3 and (Zr 0.5,Ti 0.5) 3AlC 2 Max Phase-Based Ceramics

et al. 2019

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Publisher's PDF, also known as Version of record Cyswllt i'r cyhoeddiad / Link to publication Dyfyniad o'r fersiwn a gyhoeddwyd / Citation for published version (APA): a b s t r a c tThis work is a first assessment of the radiation tolerance of the nanolayered ternary carbides (MAX phases), Zr 3 AlC 2 , Nb 4 AlC 3 and (Zr 0.5 ,Ti 0.5 ) 3 AlC 2 , using proton irradiation followed by post-irradiation examination based primarily on x-ray diffraction analysis. These specific MAX phase compounds are being evaluated as candidate coating materials for fuel cladding applications in advanced nuclear reactor systems. The aim of using a MAX phase coating is to protect the substrate fuel cladding material from corrosion damage during its exposure to the primary coolant. Proton irradiation was used in this study as a surrogate for neutron irradiation in order to introduce radiation damage into these ceramics at reactorrelevant temperatures. The post-irradiation examination of these materials revealed that the Zr-based 312-MAX phases, Zr 3 AlC 2 and (Zr 0.5 ,Ti 0.5 ) 3 AlC 2 have a superior ability for defect-recovery above 400 °C, whilst the Nb 4 AlC 3 does not demonstrate any appreciable defect recovery below 600 °C. Density functional theory calculations have demonstrated that the structural differences between the 312 and 413-MAX phase structures govern the variation of the irradiation tolerance of these materials.

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Irradiation resistance of MAX phases Ti3SiC2 and Ti3AlC2: Characterization and comparison

Cited by 51 publications

References 18 publications

Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C

Microstructure and mechanical properties of titanium aluminum carbides neutron irradiated at 400–700 °C

First-Principles Study of Vacancies in Ti3SiC2 and Ti3AlC2

The Stability of Irradiation-Induced Defects in Zr <sub>3</sub>AlC <sub>2</sub>, Nb <sub>4</sub>AlC <sub>3</sub> and (Zr <sub>0.5</sub>,Ti <sub>0.5</sub>) <sub>3</sub>AlC <sub>2</sub> Max Phase-Based Ceramics

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