In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite
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 modellin...
| Main Authors: | , , , , , |
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| Format: | Journal article |
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Elsevier
2016
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| _version_ | 1797074579330433024 |
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| author | Saucedo Mora, L Lowe, T Zhao, S Lee, P Mummery, P Marrow, T |
| author_facet | Saucedo Mora, L Lowe, T Zhao, S Lee, P Mummery, P Marrow, T |
| author_sort | Saucedo Mora, L |
| collection | OXFORD |
| description | 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. |
| first_indexed | 2024-03-06T23:38:15Z |
| format | Journal article |
| id | oxford-uuid:6e688022-9f55-4ea5-8e66-e5f2eb229910 |
| institution | University of Oxford |
| last_indexed | 2024-03-06T23:38:15Z |
| publishDate | 2016 |
| publisher | Elsevier |
| record_format | dspace |
| spelling | oxford-uuid:6e688022-9f55-4ea5-8e66-e5f2eb2299102022-03-26T19:24:13ZIn situ observation of mechanical damage within a SiC-SiC ceramic matrix compositeJournal articlehttp://purl.org/coar/resource_type/c_dcae04bcuuid:6e688022-9f55-4ea5-8e66-e5f2eb229910Symplectic Elements at OxfordElsevier2016Saucedo Mora, LLowe, TZhao, SLee, PMummery, PMarrow, TSiC-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. |
| spellingShingle | Saucedo Mora, L Lowe, T Zhao, S Lee, P Mummery, P Marrow, T In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite |
| title | In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite |
| title_full | In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite |
| title_fullStr | In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite |
| title_full_unstemmed | In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite |
| title_short | In situ observation of mechanical damage within a SiC-SiC ceramic matrix composite |
| title_sort | in situ observation of mechanical damage within a sic sic ceramic matrix composite |
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