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
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 42022414
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ANNEALING; DEFECTS; HFIR REACTOR; IRRADIATION; POINT DEFECTS; THERMAL CONDUCTIVITY; THERMAL DIFFUSIVITY
- Descriptors DEC
- CRYSTAL DEFECTS; CRYSTAL STRUCTURE; ENRICHED URANIUM REACTORS; HEAT TREATMENTS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; PHYSICAL PROPERTIES; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS; WATER MODERATED REACTORS
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)