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

DOI: 10.1016/j.jnucmat.2016.09.007 DOI Help

Authors: Luis Saucedo-mora (University of Oxford) , Tristan Lowe (University of Manchester) , Shixiang Zhao (University of Oxford) , P. D. Lee (Research Complex at Harwell) , Paul Mummery (University of Manchester) , Thomas James Marrow (University of Oxford)
Co-authored by industrial partner: No

Type: Journal Paper
Journal: Journal Of Nuclear Materials , VOL 481 , PAGES 13-23

State: Published (Approved)
Published: January 2016
Diamond Proposal Number(s): 10106

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.

Journal Keywords: silicon carbide ceramic composite;nuclear materials; computed tomography

Subject Areas: Materials, Engineering, Energy

Instruments: I12-JEEP: Joint Engineering, Environmental and Processing