NSUF 18-1237: Kinetics of irradiation defect annealing and thermal conductivity recovery in silicon carbide at high temperature
The objective of this project is to enhance understanding of the annealing of irradiation induced defects in high purity and sintered SiC samples at high temperatures. Under neutron irradiation the thermal conductivity of SiC degrades significantly, and within a certain temperature range (<900 oC) saturates at a nearly constant temperature-dependent value. This phenomenon has been consistently observed for both high purity variants (e.g. chemical vapor deposition [CVD] SiC) and lower purity sintered variants, though to different extents. Although it is well known that the irradiation-induced defects anneal out at high temperatures, the kinetics of the defect annealing processes is not well known. No prior efforts in the literature focus on the kinetics of irradiation annealing due to neutron irradiation and the resulting thermal conductivity recovery under temperature ramps in environments and at temperatures relevant for fission systems. This effort will aim to irradiate both high purity CVD SiC and lower purity sintered NITE SiC. The existing irradiated samples identified both exhibit strong impact on the thermal conductivity, which saturates at doses greater than 1 DPA. The SiC samples that will be used in this work have already been irradiated.
Дополнительная информация
| Поле | Величина |
|---|---|
| Awarded Institution | Pennsylvania State University |
| Embargo End Date | 2021-01-08 |
| Facility Tech Lead | Kory Linton, Mukesh Bachhav |
| NSUF Call | FY 2018 RTE 1st Call |
| PI | Nicholas Brown |
| Project Member | Yutai Katoh, Distinguished Research Staff - Oak Ridge National Laboratory (https://orcid.org/0000-0001-9494-5862) |
| Project Member | Nicholas Brown, Assistant Professor of Nuclear Engineering - Pennsylvania State University (https://orcid.org/0000-0002-0231-7728) |
| Project Notes | Awarded on 12/13/2017 |
| Project Type | RTE |
| Publication | Fully Ceramic Microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Sensitivity of reactor behavior during design basis accidents to fuel properties and the potential impact of the SiC defect annealing process Takaaki Koyanagi, Yutai Katoh, Kurt Terrani, Nicholas Brown Nuclear Engineering and Design 345 2019-04-15 https://doi.org/10.1016/j.nucengdes.2019.02.012 |
| RTE Number | 1237 |