Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ~100 displacements per atom
Abstract
For the development of silicon carbide (SiC) materials for next-generation nuclear structural applications, degradation of material properties under intense neutron irradiation is a critical feasibility issue. This paper evaluated the mechanical properties and microstructure of a chemical vapor infiltrated SiC matrix composite, reinforced with a multi-layer SiC/pyrolytic carbon–coated Hi-NicalonTM Type S SiC fiber, following neutron irradiation at 319 and 629 °C to ~100 displacements per atom. Both the proportional limit stress and ultimate flexural strength were significantly degraded as a result of irradiation at both temperatures. After irradiation at 319 °C, the quasi-ductile fracture behavior of the nonirradiated composite became brittle, a result that was explained by a loss of functionality of the fiber/matrix interface associated with the disappearance of the interphase due to irradiation. Finally, the specimens irradiated at 629 °C showed increased apparent failure strain because the fiber/matrix interphase was weakened by irradiation-induced partial debonding.
- Authors:
-
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- National Inst. for Quantum and Radiological Science and Technology, Rokkasho (Japan)
- Stony Brook Univ., NY (United States)
- Publication Date:
- Research Org.:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); National Inst. for Quantum and Radiological Science and Technology, Rokkasho (Japan)
- Sponsoring Org.:
- USDOE Office of Science (SC), Fusion Energy Sciences (FES); Japan Atomic Energy Agency (JAEA)
- OSTI Identifier:
- 1423016
- Grant/Contract Number:
- AC05-00OR22725; NFE-10-02779
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Journal of the European Ceramic Society
- Additional Journal Information:
- Journal Volume: 38; Journal Issue: 4; Journal ID: ISSN 0955-2219
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 36 MATERIALS SCIENCE; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; silicon carbide; ceramics matrix composite; neutron irradiation; mechanical properties
Citation Formats
Koyanagi, Takaaki, Nozawa, Takashi, Katoh, Yutai, and Snead, Lance L. Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ~100 displacements per atom. United States: N. p., 2017.
Web. doi:10.1016/j.jeurceramsoc.2017.12.026.
Koyanagi, Takaaki, Nozawa, Takashi, Katoh, Yutai, & Snead, Lance L. Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ~100 displacements per atom. United States. https://doi.org/10.1016/j.jeurceramsoc.2017.12.026
Koyanagi, Takaaki, Nozawa, Takashi, Katoh, Yutai, and Snead, Lance L. Wed .
"Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ~100 displacements per atom". United States. https://doi.org/10.1016/j.jeurceramsoc.2017.12.026. https://www.osti.gov/servlets/purl/1423016.
@article{osti_1423016,
title = {Mechanical property degradation of high crystalline SiC fiber–reinforced SiC matrix composite neutron irradiated to ~100 displacements per atom},
author = {Koyanagi, Takaaki and Nozawa, Takashi and Katoh, Yutai and Snead, Lance L.},
abstractNote = {For the development of silicon carbide (SiC) materials for next-generation nuclear structural applications, degradation of material properties under intense neutron irradiation is a critical feasibility issue. This paper evaluated the mechanical properties and microstructure of a chemical vapor infiltrated SiC matrix composite, reinforced with a multi-layer SiC/pyrolytic carbon–coated Hi-NicalonTM Type S SiC fiber, following neutron irradiation at 319 and 629 °C to ~100 displacements per atom. Both the proportional limit stress and ultimate flexural strength were significantly degraded as a result of irradiation at both temperatures. After irradiation at 319 °C, the quasi-ductile fracture behavior of the nonirradiated composite became brittle, a result that was explained by a loss of functionality of the fiber/matrix interface associated with the disappearance of the interphase due to irradiation. Finally, the specimens irradiated at 629 °C showed increased apparent failure strain because the fiber/matrix interphase was weakened by irradiation-induced partial debonding.},
doi = {10.1016/j.jeurceramsoc.2017.12.026},
journal = {Journal of the European Ceramic Society},
number = 4,
volume = 38,
place = {United States},
year = {Wed Dec 20 00:00:00 EST 2017},
month = {Wed Dec 20 00:00:00 EST 2017}
}
Web of Science