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 573-1073 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 (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. 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.
| Original language | English |
|---|---|
| Pages (from-to) | 450-457 |
| Number of pages | 8 |
| Journal | Journal of Nuclear Materials |
| Volume | 462 |
| DOIs | |
| State | Published - Jun 14 2015 |
Funding
The authors acknowledge A.M. Williams, P.S. Tedder, R.A. Meisner, and H. Wang for assistance in conducting experimental research, K.A. Terrani for technical review, and D.M Counce for editorial review. This research was sponsored by the Office of Fusion Energy Sciences, U.S. Department of Energy , and Japan Atomic Energy Agency under contracts DE-AC05-00OR22725 and NFE-10-02779 , respectively, with UT-Battelle, LLC . Samples were irradiated in the High Flux Isotope Reactor, an Office of Science User Facility.