Thermal Conductivity Degradation and Microstructural Damage Characterization in Low-Dose Ion Beam-Irradiated 3C-SiC

Chauhan, Vinay; Riyad, M. Faisal; Du, Xinpeng; Wei, Changdong; Tyburska-Püschel, B.; Zhao, Ji‐Cheng; Khafizov, Marat

doi:10.1007/s40553-017-0107-3

Cited by 11 publications

(7 citation statements)

References 76 publications

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“…In short, the thermal conductivity monotonically decreases with increasing the swelling. The result of this study is consistent with previous study on Raman spectroscopy of irradiated SiC, showing the TO and LO peak positions of 795 and 971 cm −1 , respectively, for the thermal conductivity of 150–250 W/(m K) . Therefore, the Raman peak positions are indirectly correlated with room temperature thermal conductivity, though a theoretical explanation is currently lacking.…”

Section: Discussionsupporting

confidence: 92%

Raman spectroscopy of neutron irradiated silicon carbide: Correlation among Raman spectra, swelling, and irradiation temperature

Koyanagi

Katoh

Lance

2018

J Raman Spectroscopy

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The effects of neutron irradiation on microstructural evolution and the resultant changes in physical and mechanical properties are of critical importance for the development of silicon carbide (SiC) materials for nuclear applications. This study neutron-irradiated β-SiC under a wide range of conditions at temperatures between 235 and 750°C and neutron doses of 0.01-11.8 displacements per atom, and then evaluated the effects on the SiC structure using Raman spectroscopy. The SiC optical phonon lines were shifted to

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Section: Discussionsupporting

confidence: 92%

Raman spectroscopy of neutron irradiated silicon carbide: Correlation among Raman spectra, swelling, and irradiation temperature

Koyanagi

Katoh

Lance

2018

J Raman Spectroscopy

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“…16 The cubic symmetry of β-SiC has two main bands at 796 cm −1 and 972 cm −1 , corresponding to TO and LO optical modes, respectively. 17,18 The Raman spectra of SiC fibers irradiated with 410 MeV 112 Sn 26+ ions have obvious evolution compared with the unirradiated SiC fibers. These differences are related to the modification of local structure.…”

Section: Resultsmentioning

confidence: 99%

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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“…The simplest form for the thermal wave penetration for the TDTR geometry is given as 𝐿 KL = H𝐷/(𝜋𝑓) , where D is the diffusivity of the substrate and f is the pump modulation frequency [406,569]. TDTR has been used to study a variety of ion irradiated materials including nuclear fuel [570], nuclear fuel cladding [571], silicon carbide [572] metallic multi-layers [571], silicon [571,573], sapphire [574], and diamond [575] across orders of magnitude in thermal conductivity. MTR, also referred to as spatial domain or beam-offset thermoreflectance [576,577,578,579,580,581], has been used in the majority of studies of ion irradiated actinide oxides and their surrogates.…”

Section: Experimental Measurement Of Thermal Conductivitymentioning

confidence: 99%

Thermal Energy Transport in Oxide Nuclear Fuel

et al. 2021

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To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts seek solid fuels that must withstand unprecedented temperature and radiation extremes. In these advanced fuels, thermal energy transport under irradiation is directly related to reactor performance as well as reactor safety. The science of thermal transport in nuclear fuel is a grand challenge due to both computational and experimental complexities. Here, we provide a comprehensive review of thermal transport research on two actinide oxides: one currently in use in commercial nuclear reactors, uranium dioxide (UO2), and one advanced fuel candidate material, thorium dioxide (ThO2). In both materials, 5Concluding Remarks .

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Thermal Conductivity Degradation and Microstructural Damage Characterization in Low-Dose Ion Beam-Irradiated 3C-SiC

Cited by 11 publications

References 76 publications

Raman spectroscopy of neutron irradiated silicon carbide: Correlation among Raman spectra, swelling, and irradiation temperature

Raman spectroscopy of neutron irradiated silicon carbide: Correlation among Raman spectra, swelling, and irradiation temperature

Microstructure of SiC fibers by swift heavy ion beam irradiation

Thermal Energy Transport in Oxide Nuclear Fuel

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