The effect of neutron irradiation on the fiber/matrix interphase of silicon carbide composites

T. Nozawa, Y. Katoh, L. L. Snead

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Abstract

Given the good stability of mechanical properties of silicon carbide (SiC) under neutron irradiation, the ultimate irradiation tolerance of SiC composite materials may be limited by the fiber/matrix interphase, which is critically important to the performance of these composites. This study investigates the irradiation stability of pyrolytic carbon (PyC) monolayer and PyC/SiC multilayer interphases by tensile and single fiber push-out test techniques. Neutron irradiation was performed to doses of 0.7-7.7 dpa at temperatures from 380 to 1080 °C. Both interfacial debond shear strength and interfacial friction stress apparently decrease by irradiation, although this is not so dramatic when Tirr < 1000 °C. In contrast, the interfacial shear stresses are most affected by the higher temperature irradiation (>1000 °C). Noteworthy, these irradiation effects depend on the type of interphase material, i.e., for the pyrolytic carbon or multilayer SiC variants studied. In the range of irradiation temperature and dose, the degradation in interfacial shear properties, while measurable, is not of a magnitude to degrade the mechanical performance of the composites. This was observed for both interphase types studied. In particular, the proportional limit tensile stress decreases slightly by irradiation while the tensile fracture strength undergoes very minor change.

Original languageEnglish
Pages (from-to)195-211
Number of pages17
JournalJournal of Nuclear Materials
Volume384
Issue number3
DOIs
StatePublished - Feb 28 2009

Funding

The authors would like to thank Dr R.J. Shinavski for fabricating materials, and Dr J.T. Busby, Ms A.M. Williams and Ms P.S. Tedder for post-irradiation experiments. The special thanks are extended to Dr T.S. Byun for reviewing the manuscript. Additionally, the authors would like acknowledge the use of the High Flux Isotope Reactor user facility. This research was sponsored by the Office of Fusion Energy Sciences, US Department of Energy under contract DE-AC05-00OR22725 with UT-Battelle, LLC and by the US Department of Energy Office of Nuclear Energy, Science and Technology, a Nuclear Energy Research Initiative (NERI) Project, under Contract NEAF355 (AF3510) with Oak Ridge National Laboratory (operated by UT-Battelle, LLC). This study was also a part of ‘JUPITER-II’ US-Department of Energy/Japanese Ministry of Education, Culture, Sports, Science and Technology (MEXT) collaboration for fusion material system research.

FundersFunder number
Nuclear Energy Research InitiativeAF3510, NEAF355
US Department of Energy Office of Nuclear Energy, Science and Technology
US-Department of Energy/Japanese Ministry of Education, Culture, Sports, Science and Technology
U.S. Department of EnergyDE-AC05-00OR22725
Fusion Energy Sciences
Oak Ridge National Laboratory
Ministry of Education, Culture, Sports, Science and Technology

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