Evaluation of damage tolerance of neutron-irradiated SiC/SiC composites

Ozawa, Kazumi; Kato, Yutai*; Nozawa, Takashi; Snead, L. L.*

Advanced SiC/SiC composites are candidates for the advanced blanket material for fusion DEMO reactor. In order to investigate the effects of neutron irradiation on fracture resistance, the composites after neutron irradiation to 5.9 10 $^{25}$ n/m $^{2}$ ( 0.1 MeV) at 800 and 1300 $^{circ}$ C were evaluated by three-point single edge notched bend miniature test. Taking all results into consideration for the global energy balance analysis based on the non-linear fracture mechanics, the previous tensile tests, and the hysteresis loop analysis for interfacial property evaluation, it was concluded that the effects of neutron irradiation in conditions studied on fracture resistance of the composites appeared insignificant.

Language	:	English
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Meeting title	:	15th International Conference on Fusion Reactor Materials (ICFRM-15)
Held date	:	2011/10
Location (city)	:	Charleston
Location (country)	:	U.S.A.
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Keywords	:	no keyword
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Cooperating Institute	:	Oak Ridge National Laboratory

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Registration No. : BB20111740
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