In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite
File(s)
Published version
Author(s)
Type
Journal Article
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.
Date Issued
2016-09-12
Date Acceptance
2016-09-08
Citation
Journal of Nuclear Materials, 2016, 481 (2016), pp.13-23
ISSN
1873-4820
Publisher
Elsevier
Start Page
13
End Page
23
Journal / Book Title
Journal of Nuclear Materials
Volume
481
Issue
2016
Copyright Statement
©
2016 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY license
(
http://creativecommons.org/licenses/by/4.0/
).
2016 The Authors. Published by Elsevier B.V. This is an open access article under the CC BY license
(
http://creativecommons.org/licenses/by/4.0/
).
Identifier
http://gateway.webofknowledge.com/gateway/Gateway.cgi?GWVersion=2&SrcApp=PARTNER_APP&SrcAuth=LinksAMR&KeyUT=WOS:000386822900002&DestLinkType=FullRecord&DestApp=ALL_WOS&UsrCustomerID=1ba7043ffcc86c417c072aa74d649202
Subjects
Science & Technology
Technology
Physical Sciences
Materials Science, Multidisciplinary
Nuclear Science & Technology
Mining & Mineral Processing
Materials Science
SILICON-CARBIDE COMPOSITES
NEUTRON-IRRADIATION
BEHAVIOR
TEMPERATURES
STRENGTH
FAILURE
STRESS
TUBES
Energy
0912 Materials Engineering
Publication Status
Published