2014
DOI: 10.1017/s143192761401085x
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High-Resolution Scanning Transmission Electron Microscopy Study of Black Spot Defects in Ion Irradiated Silicon Carbide

Abstract: Silicon carbide is of great interest as a structural material in nuclear systems because of its high strength, corrosion resistance and high thermal conductivity. An important material property related to failure is irradiation induced volume increase, or swelling. Swelling saturates in silicon carbide at relatively low irradiation temperatures (~< 1000 °C) and doses (~< 10 dpa or displacements per atom), when the major defects appear in bright field transmission electron microscopy (TEM) images as nanometer s… Show more

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Cited by 4 publications
(5 citation statements)
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“…The C SI for neutron and self ion irradiations are approximately expected to be 1×10 24 -1×10 26 at•m −3 . In particular, C SI for C + irradiated 4H-SiC, which was irradiated under conditions similar to those used in this study (similar radiation source, temperature, and dpa), is estimated to be 2.6×10 24 at•m −3 [61]. The C + irradiated 4H-SiC data will be used for the present analysis as it is the available data with the most similar irradiation conditions to the experiments performed here.…”
Section: Self-interstitial As a Source For Kickout Reactionsmentioning
confidence: 86%
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“…The C SI for neutron and self ion irradiations are approximately expected to be 1×10 24 -1×10 26 at•m −3 . In particular, C SI for C + irradiated 4H-SiC, which was irradiated under conditions similar to those used in this study (similar radiation source, temperature, and dpa), is estimated to be 2.6×10 24 at•m −3 [61]. The C + irradiated 4H-SiC data will be used for the present analysis as it is the available data with the most similar irradiation conditions to the experiments performed here.…”
Section: Self-interstitial As a Source For Kickout Reactionsmentioning
confidence: 86%
“…Here we assume that the SI density in BSDs is the same as that of Si and C in SiC. In Table 3, TEM observations on BSD concentration and size from Ref [60,61] are summarized, and the SI concentrations are estimated for each set of data under the assumption that the BSDs are fully dissolved. The C SI for neutron and self ion irradiations are approximately expected to be 1×10 24 -1×10 26 at•m −3 .…”
Section: Self-interstitial As a Source For Kickout Reactionsmentioning
confidence: 99%
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“…Although not conducted here, the application of aberration-corrected STEM where pointto-point resolutions ;1 Å are routinely possible, could be used to characterize the morphology of the "black dot" damage typical of irradiated BCC Fe and BCC Fe-Cr at low temperatures. Ultrahigh resolution analysis of black spot damage in SiC has already been shown, 90 and extension to ferritic steels should be possible.…”
Section: Dislocation Loop Imagingmentioning
confidence: 95%
“…Although it has been hypothesized that both radiation swelling and radiation creep are driven by formation of defect clusters, existing models for swelling and creep in SiC are limited by the lack of understanding of specific defects that form due to radiation in the range of temperatures relevant to fuel cladding in light water reactors (LWRs) (<1000°C) [1,2]. For example, defects that can be detected with traditional transmission electron microscopy (TEM) techniques account only for 10-45% of the swelling measured in irradiated SiC.…”
Section: Introductionmentioning
confidence: 99%