Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
7966093 | Journal of Nuclear Materials | 2015 | 8 Pages |
Abstract
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 573-1073Â K. 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 (1073Â K) to very severe (573Â K) degradation in mechanical properties was found after irradiation to >70Â 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. 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.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Yutai Katoh, Takashi Nozawa, Chunghao Shih, Kazumi Ozawa, Takaaki Koyanagi, Wally Porter, Lance L. Snead,