Irradiation-induced shrinkage of highly crystalline SiC fibers

Kondo, Sosuke; Hinoki, Tatsuya; Nonaka, Makoto; Ozawa, Kazumi

doi:10.1016/j.actamat.2014.07.057

Cited by 39 publications

(17 citation statements)

References 41 publications

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“…Nozawa et al report a major reduction in fiber/matrix interfacial debond stress and a mild reduction in interfacial frictional stress. A recent ion irradiation experiment by Kondo et al [35], showing a very significant differential swelling between the CVI SiC matrix and Hi-Nicalon Type S fiber at 573 K and 100 dpa, implies the development of strong tensile stress across the interface during irradiation at this temperature. The lack of post-linear flexural behavior and the lack of fiber pullout even with significant interfacial degradation enhances the already strong case for a loss of fiber toughness.…”

Section: Degradation Mechanismmentioning

confidence: 96%

High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties

Katoh

Nozawa

Shih

et al. 2015

Journal of Nuclear Materials

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a b s t r a c tNuclear-grade silicon carbide (SiC) composite material was examined for mechanical and thermophysical properties following high-dose neutron irradiation in the High Flux Isotope Reactor at a temperature range of 573-1073 K. The material was chemical vapor-infiltrated SiC-matrix composite with a twodimensional satin weave Hi-Nicalon Type S SiC fiber reinforcement and a multilayered pyrocarbon/SiC interphase. Moderate (1073 K) to very severe (573 K) degradation in mechanical properties was found after irradiation to >70 dpa, whereas no evidence was found for progressive evolution in swelling and thermal conductivity. The swelling was found to recover upon annealing beyond the irradiation temperature, indicating the irradiation temperature, but only to a limited extent. The observed strength degradation is attributed primarily to fiber damage for all irradiation temperatures, particularly a combination of severe fiber degradation and likely interphase damage at relatively low irradiation temperatures.

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Section: Degradation Mechanismmentioning

confidence: 96%

High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties

Katoh

Nozawa

Shih

et al. 2015

Journal of Nuclear Materials

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“…2(a) and 2(b). 19 It should be noted that the carbon ribbons was progressively reduced in third generation SiC fibers irradiated with 5 × 10 13 ions/cm 2 dose, as shown in Fig. 2(b), and completely disappeared surrounding the third generation SiC particle at 1.5 × 10 15 ions/cm 2 dose, as shown in Fig.…”

Section: Resultsmentioning

confidence: 81%

Microstructure of SiC fibers by swift heavy ion beam irradiation

et al. 2019

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In this paper, third generation SiC fiber material irradiated with the 410 MeV energy of [Formula: see text] ion at 173 K was analyzed by Raman spectroscopy, X-ray diffraction (XRD) and transmission electron microscope (TEM). Raman spectroscopy, TEM and XRD data show modifications in the local structure of irradiated SiC fibers. Although highly disordered SiC grains were observed in appearance, no evidence of amorphization was found. After the Sn ions irradiation and XRD, two diffraction peaks disappeared, which showed that the rich Si and C could be further combined in [Formula: see text] ions/cm2 dose irradiation condition. This result mainly explains the electron damage and the nuclear damage process in SiC fibers, leading to the recombination or migration of defects.

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“…Owing to its excellent mechanical and structural properties, silicon carbide (SiC) has been proposed for structure and cladding materials for a nuclear and an aerospace environment. [1][2][3] In these harsh environments, however, the high-dose irradiation will induce swelling and creep in SiC-based components, degrading the mechanical property of the SiC and greatly decreasing the lifetime of the SiC-based components. 3 Functionally, owing to its superior electronic, optical, and physical properties, SiC is also an important wide-bandgap semiconductor material with applications in hightemperature, high-power, and high-frequency electronic devices.…”

Section: Introductionmentioning

confidence: 99%

“…Up to now, considerable research efforts have been made to explore the swelling in SiC after neutron irradiation [7][8][9] and ion implantation. 1,3,10 It is generally accepted that defects introduced by irradiation play an important role in the strain and swelling accumulation. Under varying irradiation conditions, including varying temperatures 2 or irradiation fluences, 11 the swelling changes greatly because of different types of defects formed under different irradiation conditions, i.e., point defects, defect clusters, voids, and bubbles.…”

Section: Introductionmentioning

confidence: 99%

Electron energy-loss spectroscopic evaluation of depth-dependent swelling of He+ ion-irradiated 4H-SiC correlated with defect type

Yang

Nakagawa

Kondo

et al. 2020

Journal of Applied Physics

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Various defects and amorphous transitions are the primary mechanism behind the accumulation of swelling in silicon carbide (SiC). In this study, selected-area He + ion irradiation was carried out on single-crystal 4H-SiC using fluences of 1 × 10 15 , 5 × 10 16 , and 1 × 10 17 cm −2 at room temperature. The defect distribution in the samples with varying irradiation fluences was analyzed using transmission electron microscopy (TEM), while the local swelling of regions under varying damage conditions was estimated using electron energy-loss spectroscopy. The results provide the range of swelling in SiC possessing different primary defect types, such as point defects or tiny clusters, black spot defects, and amorphous SiC. A saturation swelling with a value of 2%-3% in the near-surface region, induced by point defects or tiny clusters (invisible in TEM), was observed at room temperature over the fluence range of 1 × 10 15 to 1 × 10 17 cm −2 . This saturation has already reached at a great low dose of about 0.02 dpa. The swelling of the region containing black spot defects ranges from about 3% to 7%. Helium bubbles increase the volume swelling of SiC, while the He + ion irradiation may also perform a decreasing effect on the volume swelling below a certain irradiation fluence.

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Irradiation-induced shrinkage of highly crystalline SiC fibers

Cited by 39 publications

References 41 publications

High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties

High-dose neutron irradiation of Hi-Nicalon Type S silicon carbide composites. Part 2: Mechanical and physical properties

Microstructure of SiC fibers by swift heavy ion beam irradiation

Electron energy-loss spectroscopic evaluation of depth-dependent swelling of He+ ion-irradiated 4H-SiC correlated with defect type

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