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Mechanical and thermo-physical characterization of three-directional carbon fiber composites for W-7X and ITER
- Source :
- Fusion Engineering and Design, Fusion Engineering and Design, v.84, 1525-1530 (2009)
- Publication Year :
- 2009
- Publisher :
- Elsevier BV, 2009.
-
Abstract
- Carbon fiber composites (CFCs) are the first choice as plasma facing materials for the strike points of divertor targets for future nuclear fusion devices like WENDELSTEIN 7-X and ITER. For the application in these facilities several potential European 3D-CFCs were compared and qualified: (1) four material batches of NB31 produced by Snecma Propulsion Solide (SNECMA); (2) NB41, SNECMA, the upgraded version of NB31; (3) N31, SNECMA, which is densified by chemical vapor infiltration (CVI) instead of a final liquid pitch infiltration characteristic for NB31; (4) a new developmental 3D-CFC produced by DUNLOP. The characterization of the composites is comprised of thermo-physical measurements and tensile tests. The results are correlated to density and microstructure and summarized as follows: (1) NB41 provides the highest thermal conductivity in the ex-pitch direction of ∼375 W/(m K) at room temperature; (2) all material grades are, due to their heterogeneity, characterized by a relatively large scatter of mechanical properties; (3) the different densification process for N31 in comparison to NB31 has no influence on the material properties; (4) NB41 provides in all three directions a comparably high tensile strength with an average in the ex-pitch direction of ∼220 MPa; (5) the 3D-CFC from DUNLOP is comparable to NB41 but yet does not meet the specifications in the needling direction.
- Subjects :
- Materials science
Mechanical Engineering
Divertor
Fusion power
Microstructure
Thermal conductivity
Nuclear Energy and Engineering
Chemical vapor infiltration
Ultimate tensile strength
General Materials Science
Composite material
Material properties
Civil and Structural Engineering
Tensile testing
Subjects
Details
- ISSN :
- 09203796
- Volume :
- 84
- Database :
- OpenAIRE
- Journal :
- Fusion Engineering and Design
- Accession number :
- edsair.doi.dedup.....219a0257171e04ed1826bae73c0323d6