Effect of Neutron Irradiation on Tensile Properties of Unidirectional Silicon Carbide Composites

Journal Article · Mon Jan 01 00:00:00 EST 2007 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2007.03.083· OSTI ID:978204

Katoh, Yutai ^[1]; Nozawa, Takashi ^[1]; Snead, Lance Lewis ^[1]; Hinoki, Tatsuya ^[1]

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1. ORNL

Tensile properties of uni-directionally reinforced Hi-Nicalon EType S SiC fiber, chemically vapor-infiltrated (CVI) SiC-matrix composites, with either pyrolytic carbon (PyC) or multilayered PyC/SiC interphase, were characterized following neutron irradiations to the maximum fluence of 7.7x1025 n/m2 at 380 and 800 C. The stress - strain behavior of the multilayered interphase composites remained unmodified after irradiation. The PyC interphase composite increased in ultimate tensile stress and strain to failure following neutron irradiation, whereas the proportional limit stress exhibited a slight decrease. Potential mechanisms for these changes include accommodation of misfit stress through irradiation creep, reduced interfacial friction, and differential swelling among individual composite constituents.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)
• Sponsoring Organization: USDOE Office of Science (SC)
• DOE Contract Number: DE-AC05-00OR22725
• OSTI ID: 978204
• Journal Information: Journal of Nuclear Materials, Vol. 367, Issue 1
• Country of Publication: United States
• Language: English