Plastic Deformation and Cracking Resistance of SiC Ceramics Measured by Indentation

Wade, James B.; Claydon, P.; Wu, Houzheng

doi:10.1002/9781119031192.ch10

Cited by 8 publications

(9 citation statements)

References 9 publications

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“…During irradiation, the chamber was maintained in vacuum with a pressure < 10 -3 Pa; the ion beam direction was set perpendicular to the surface of irradiated surface. The energy of the ion beam was 4 MeV, and an accumulated ion fluence of 5x10 16 /cm 2 was implanted on the surface of each irradiated sample.…”

Section: Au Ion Irradiationmentioning

confidence: 99%

Structural integrity and characteristics at lattice and nanometre levels of ZrN polycrystalline irradiated by 4 MeV Au ions

Bao

Robertson

Liu

et al. 2018

Journal of the European Ceramic Society

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We report an as-hot-pressed zirconium nitride polycrystalline with its primary crystal structure maintained no change but lattice defects and features were introduced at nanometre-scale after being irradiated by 4 MeV Au 2+ with a total fluence of 5x10 16 /cm 2. The variation of grey-level seen in backscattered electron images and electron backscattered diffraction maps directly evidenced the structure integrity of the polycrystalline ZrN is well maintained with no crystal structure change of ZrN. The irradiation depth had no relevance to crystal orientation, and Au deposition peaked at a depth of ~0.58 μm with a near-Gaussian distribution. Within a depth <0.58 μm, long dislocation lines were developed with a Burgers vector of [011 ]b/2 and density 3.2x10 14 1/m 2 ; beyond this depth, dislocation loops were formed with much higher density. In the ionization zone, cubic ZrO2 crystallites precipitated in a size of ~5 nm. The irradiation damage processes are discussed based on the observed features.

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Section: Au Ion Irradiationmentioning

confidence: 99%

Structural integrity and characteristics at lattice and nanometre levels of ZrN polycrystalline irradiated by 4 MeV Au ions

Bao

Robertson

Liu

et al. 2018

Journal of the European Ceramic Society

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“…After indentation testing, all the impressions were imaged using a scanning probe microscopy (SPM) provided by the indentation system to measure the length of the radial cracks emitted from their corners. The length of the radial cracks in the SPM images was measured using a graphic editing software (Adobe Photoshop, USA) . Hardness and elastic modulus were measured using a Berkovich indenter on the same instrument.…”

Section: Methodsmentioning

confidence: 99%

“…The length of the radial cracks in the SPM images was measured using a graphic editing software (Adobe Photoshop, USA). 19,20 Hardness and elastic modulus were measured using a Berkovich indenter on the same instrument. The indentation load was 9 mN for all the hardness tests.…”

Section: Nanoindentationmentioning

confidence: 99%

New insights into nanoindentation crack initiation in ion‐exchanged sodium aluminosilicate glass

Jiang

Mohagheghian

et al. 2018

J Am Ceram Soc

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The effect of ion‐exchange on the fracture behavior and the threshold load is investigated for radial crack initiation resulting from cube‐corner indentation. Both tin and air sides of the sodium aluminosilicate float glass are considered. The threshold load and mechanical properties are experimentally measured by nanoindentation. A qualitative explanation of crack initiation is developed by analyzing the stresses at the indentation site. The ion‐exchanged glasses show a lower threshold load for radial crack initiation with a cube‐corner indenter than the raw glass, and this is due to a higher crack driving stress for ion‐exchanged glasses. However, the compressive stress on the surface of the ion‐exchanged glasses can inhibit the expanding of the radial cracks. The air side always shows higher values for the threshold load than the tin side before and after ion‐exchange, which is in accordance with the calculated crack driving stress results.

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“…As can be seen from the obtained data, hardness and fracture toughness values are not principally changed for both samples with additive Cr and Si. SiC Previously was reported, that dense and uniform SiC ceramics demonstrate high mechanical parameters: micro hardness 24 GPa [32,33] and fracture toughness coefficient K 1c = 5 MPa•m 1/2. [32].…”

Section: Eejp 4 2018mentioning

confidence: 99%

“…SiC Previously was reported, that dense and uniform SiC ceramics demonstrate high mechanical parameters: micro hardness 24 GPa [32,33] and fracture toughness coefficient K 1c = 5 MPa•m 1/2. [32]. At present study, SiC ceramic samples with Si, Cr and without additives also show high mechanical parameters: micro hardness 29.8 GPa and fracture toughness coefficient K 1c =4.5 MPa•m 1/2 .…”

Section: Eejp 4 2018mentioning

confidence: 99%

Physical-Mechanical Properties of γ-Irradiated SiC Ceramics for Radioactive Wastes Immobilization

Lobach

Sayenko

Shkuropatenko

et al. 2018

EEJP

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The interest in silicon carbide (SiC-based) ceramics and composites as matrix material for nuclear waste immobilization is grown up. Long-term chemical durability and radiation resistance of SiC are important factors for radionuclides immobilization. Advantages of SiC-based ceramics as structural materials in nuclear applications are the high-temperature properties, high density and reduced neutron activation. The use of radiation resistant materials is a strong requirement for safe and environmentally beneficial energy system. The SiC ceramics stability under irradiation for temperatures up to 1273 K is also very important for nuclear power applications. The SiC matrices doped by additives of Cr, Si were fabricated using High Speed Hot Pressing Method. Additives content was in the range from 0.5 to 3 wt %. Microstructural characteristics of silicon carbide ceramics were analyzed by X-ray diffraction (XRD), scanning electron microscopy (SEM), energy-dispersive X-ray spectroscopy (EDX), and infra-red spectroscopy (IR) methods. The results of microcracking under indentation conditions were revealed the lack of cracks in the SiC ceramics with Cr additives before and after irradiation process. In addition, it was demonstrated that samples of SiC with alloying additives Cr and Si possess high mechanical parameters under γ-irradiation process. The strength of ceramics increases with the uniform and fine-grained structure formation. The modification of phase composition and mechanical properties of the SiC ceramics with Cr and Si additives under γ-irradiation were analyzed for further development of radiation resistant and matrix materials for radioactive wastes immobilization.

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Plastic Deformation and Cracking Resistance of SiC Ceramics Measured by Indentation

Cited by 8 publications

References 9 publications

Structural integrity and characteristics at lattice and nanometre levels of ZrN polycrystalline irradiated by 4 MeV Au ions

Structural integrity and characteristics at lattice and nanometre levels of ZrN polycrystalline irradiated by 4 MeV Au ions

New insights into nanoindentation crack initiation in ion‐exchanged sodium aluminosilicate glass

Physical-Mechanical Properties of γ-Irradiated SiC Ceramics for Radioactive Wastes Immobilization

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