High Dose Neutron Irradiation of Hi-Nicalon Type S Silicon Carbide Composites, Part 2. Mechanical and Physical Properties

Katoh, Yutai; Nozawa, Takashi; Shih, Chunghao Phillip; Ozawa, Kazumi; Koyanagi, Takaaki; Porter, Wallace D; Snead, Lance Lewis

doi:10.1016/j.jnucmat.2014.12.121

Title: High Dose Neutron Irradiation of Hi-Nicalon Type S Silicon Carbide Composites, Part 2. Mechanical and Physical Properties

Journal Article · Wed Jan 07 00:00:00 EST 2015 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2014.12.121· OSTI ID:1195802

Katoh, Yutai ^[1]; Nozawa, Takashi ^[2]; Shih, Chunghao Phillip ^[1]; Ozawa, Kazumi ^[1]; Koyanagi, Takaaki ^[1]; Porter, Wallace D ^[1]; Snead, Lance Lewis ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Japan Atomic Energy Agency (JAEA), Aomori-ken (Japan)

Nuclear-grade silicon carbide (SiC) composite material was examined for mechanical and thermophysical properties following high-dose neutron irradiation in the High Flux Isotope Reactor at a temperature range of 573–1073 K. Likewise, the material was chemical vapor-infiltrated SiC-matrix composite with a two-dimensional satin weave Hi-Nicalon Type S SiC fiber reinforcement and a multilayered pyrocarbon/SiC interphase. Moderate (1073 K) to very severe (573 K) degradation in mechanical properties was found after irradiation to >70 dpa, whereas no evidence was found for progressive evolution in swelling and thermal conductivity. The swelling was found to recover upon annealing beyond the irradiation temperature, indicating the irradiation temperature, but only to a limited extent. Moreover, the observed strength degradation is attributed primarily to fiber damage for all irradiation temperatures, particularly a combination of severe fiber degradation and likely interphase damage at relatively low irradiation temperatures.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States). High Flux Isotope Reactor (HFIR)

Sponsoring Organization:: USDOE Office of Science (SC), Fusion Energy Sciences (FES)

Grant/Contract Number:: AC05-00OR22725

OSTI ID:: 1195802

Alternate ID(s):: OSTI ID: 1246604

Journal Information:: Journal of Nuclear Materials, Vol. 462, Issue 6; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 49 works

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Ion irradiation effect on spark plasma sintered silicon carbide ceramics with nanostructured ferritic alloy aid Ning, Kaijie; Lu, Kathy Journal of the American Ceramic Society, Vol. 101, Issue 8 https://doi.org/10.1111/jace.15511	journal	March 2018
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Microstructure of SiC fibers by swift heavy ion beam irradiation Song, Yin; Zhang, Chong-Hong; Yang, Yi-Tao Modern Physics Letters B, Vol. 33, Issue 20 https://doi.org/10.1142/s0217984919502361	journal	July 2019

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