Published August 1, 2004 | Version v1
Miscellaneous

Effects of Irradiation and Post-Irradiation Annealing on the Thermal Conductivity/ Diffusivity of Monolithic SIC and SIC/SIC Composites

Description

Laser flash thermal diffusivity measurements were made on high-purity monolithic CVD-SiC (impurity concentration <5 wppm) and 2D f-SiC/PyC/ICVI-SiC composite samples (plain weave Hi-Nicalon (Trademark) fabric layers with 0-90 layup made by the isothermal chemical vapor infiltration process and with either a ''thick'' 1.0 (micro)m or a ''thin'' 0.11 (micro)m PyC fiber coating) before and after irradiation in the HFIR reactor (250 to 800 C, 4-8 dpa-SiC) and after post-irradiation annealing composite samples to 1200 C. Thermal conductivity in SiC is controlled by phonon transport. Point defects introduced into SiC during neutron irradiation are effective scattering centers for phonons, and as a consequence the thermal conductivity is sharply reduced. For irradiation temperatures below ∼800 C, the accumulation of point defects (in SiC mostly single or small clusters of interstitials and isolated vacancies) saturates when the interstitial-vacancy recombination rate equals the defect production rate. For saturation conditions, the relative reduction in the SiC thermal conductivity decreases in a manner similar to its swelling reduction with increasing irradiation temperature. Examination of SiC swelling data at various irradiation temperatures and doses indicates that saturation occurs for ∼2 dpa-SiC at 200 C and decreases continuously to ∼0.4 dpa-SiC at 800 C. Based on a model that assumes a uniform distribution of the phonon scattering defects, the calculated defect concentration for unirradiated CVD-SiC was less than 1 appm, which is consistent with the manufacturer's value of <5 wppm impurities. The defect concentrations estimated for the irradiated CVD-SiC samples decreased continuously from ∼25,000 to 940 appm as the irradiation temperature increased from 252 to 800 C. The small intrinsic defect concentration in comparison to the rather large extrinsic irradiation-induced defect concentrations illustrates why CVD-SiC makes an ideal irradiation damage monitor.

Additional details

Publishing Information

Publisher
RL Klueth and Teresa Roe; DOE Office of Fusion Energy Sciences
Imprint Place
Washington, DC (United States)
Imprint Pagination
vp.
Report number
PNNL-SA--40902

Optional Information

Contract/Grant/Project number
AT6020100; AC06-76RL01830
Notes
Fusion Materials Semiannual Progress Report for Period Ending December 31, 2003, 35:18-19; This record replaces 39007222
Funding organization
US Department of Energy (United States)