Abstract
The initial results of a post-irradiation examination study conducted on CVD SiC tubular specimens irradiated under a high radial heat flux are presented herein. The elastic moduli were found to decrease more than that estimated based on previous studies. The significant decreases in modulus are attributed to the cracks present in the specimens. The stresses in the specimens, calculated through finite element analyses, were found to be greater than the expected strength of irradiated specimens, indicating that the irradiation-induced stresses caused these cracks. The optical microscopy images and predicted stress distributions indicate that the cracks initiated at the inner surface and propagated outward.
| Original language | English |
|---|---|
| Pages (from-to) | 107-110 |
| Number of pages | 4 |
| Journal | Journal of Nuclear Materials |
| Volume | 499 |
| DOIs | |
| State | Published - Feb 2018 |
Funding
This research was supported by the Advanced Fuels Campaign of the Nuclear Technology R&D program within the United States Department of Energy (DOE) Office of Nuclear Energy . This work was prepared under contact DE-AC05-00OR22725 with Oak Ridge National Laboratory (ORNL) managed by UT Battelle, LLC. A portion of this research used resources at the High Flux Isotope Reactor, which is funded by the DOE Office of Basic Energy Sciences . This work also used resources at the High Temperature Materials Laboratory at ORNL. Technical advice and critical review of this document by Dr. Amit Shyam (ORNL) is gratefully acknowledged.
| Funders | Funder number |
|---|---|
| U.S. Department of Energy | |
| Office of Nuclear Energy | |
| Basic Energy Sciences |
Keywords
- Accident tolerant fuel
- Cladding
- LWR
- Nondestructive testing
- Nuclear
- SiC
- Silicon carbide