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.
Highlights
Due to their high temperature capability and damage tolerance, SiC-SiCfibre ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear fission reactor concepts such as the gas cooled fast reactor (GFR) [1]
Saucedo-Mora et al / Journal of Nuclear Materials 481 (2016) 13e23 pyrolytic carbon interphase and a b-SiC matrix formed by chemical vapour infiltration); these materials are thermally stable and retain their strength and toughness to temperatures above 1600 C
The expected structural design criterion for SiC-SiCfibre composites will be some fraction of the proportional limit stress (PLS) [19]
Summary
Due to their high temperature capability and damage tolerance, SiC-SiCfibre ceramic matrix composites are candidate materials for fuel cladding in Generation IV nuclear fission reactor concepts such as the gas cooled fast reactor (GFR) [1] [8]) provide an assessment of the average properties of the composite, and are crucial data for design Such tests may be used to evaluate the effects of irradiation and oxidation, batch-batch variations in properties and the sensitivity to composite fabrication; different composite weaves will develop different patterns of stress in the matrix [9], and heterogeneities in the weave will be responsible for variations in the onset of matrix damage and interface failures [10,11]. Component tests will be critical to evaluate the complex structures of joints [12]
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