In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite

L. Saucedo-Mora, T. Lowe, S. Zhao, P. D. Lee, P. M. Mummery, T. J. Marrow

    Research output: Contribution to journalArticlepeer-review

    Abstract

    SiC-SiC ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear fission reactors and as accident tolerant fuel clad in current generation plant. Experimental methods are needed that can detect and quantify the development of mechanical damage, to support modelling and qualification tests for these critical components. In situ observations of damage development have been obtained of tensile and C-ring mechanical test specimens of a braided nuclear grade SiC-SiC ceramic composite tube, using a combination of ex situ and in situ computed X-ray tomography observation and digital volume correlation analysis. The gradual development of damage by matrix cracking and also the influence of non-uniform loading are examined.

    Original languageEnglish
    Pages (from-to)13-23
    Number of pages11
    JournalJournal of Nuclear Materials
    Volume481
    DOIs
    Publication statusPublished - 1 Dec 2016

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