| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Composite Materials for Nuclear Applications
|
| Presentation Title |
Post-irradiation Examinations of TRISO Particles Corroded in Molten FLiBe Salt under Neutron Irradiation |
| Author(s) |
Guiqiu Tony Zheng, David Carpenter |
| On-Site Speaker (Planned) |
Guiqiu Tony Zheng |
| Abstract Scope |
Several advanced reactor designs incorporate tri-structural isotropic (TRISO) fuel particles with SiC and pyrolytic carbon coating layers to achieve fuel compatibility with high coolant temperatures and increased thermodynamic efficiency. TRISO particles embedded in graphite matrix fuel pebbles are being considered as a fuel for fluoride salt-cooled high-temperature reactors (FHRs). In support of FHR development, TRISO particles with ZrO2 surrogate kernels were tested in Li-7 enriched FLiBe (2LiF-BeF2) salt at 700°C for 1000 hours in the Massachusetts Institute of Technology Research Reactor (MITR) to evaluate their behavior in case of direct salt contact with the particles in the FHR. In this study nano-scale microstructural characterizations were performed to examine the condition of the TRISO particles post-irradiation. The synergistic effects of molten salt exposure and neutron irradiation at high temperature caused tangential cracks to form in the SiC layer and molten salt to infiltrate into the particle along these cracks. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Ceramics |