Journal article
In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite
- 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.
- Publication status:
- Published
- Peer review status:
- Peer reviewed
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(Preview, Version of record, pdf, 3.4MB, Terms of use)
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- Publisher copy:
- 10.1016/j.jnucmat.2016.09.007
Authors
+ Engineering and Physical Sciences Research Council
More from this funder
- Funding agency for:
- Saucedo Mora, L
- Marrow, T
- Grant:
- EP/K032518/1
- EP/J019992/1
- Publisher:
- Elsevier
- Journal:
- Journal of Nuclear Materials More from this journal
- Volume:
- 481
- Pages:
- 13–23
- Publication date:
- 2016-10-12
- Acceptance date:
- 2016-09-08
- DOI:
- ISSN:
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0022-3115
- Pubs id:
-
pubs:641749
- UUID:
-
uuid:6e688022-9f55-4ea5-8e66-e5f2eb229910
- Local pid:
-
pubs:641749
- Source identifiers:
-
641749
- Deposit date:
-
2016-09-08
Terms of use
- Copyright holder:
- Saucedo-Mora et al
- Copyright date:
- 2016
- Notes:
- © 2016 The Authors. Published by Elsevier B.V. Open Access funded by Engineering and Physical Sciences Research Council. Under a Creative Commons license.
- Licence:
- CC Attribution (CC BY)
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