| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Irradiation Testing: Facilities, Capabilities, and Experimental Designs
|
| Presentation Title |
Deployment and Testing of a Fiber-based Instrument for In-reactor Thermal Property Measurements at MIT Research Reactor |
| Author(s) |
Zilong Hua, Caleb Picklesimer, Robert Schley, Colby Jensen, Austin Fleming, Weiyue Zhou, Michael Short, David Carpenter |
| On-Site Speaker (Planned) |
Zilong Hua |
| Abstract Scope |
The thermal conductivity of nuclear fuels is a critical physical property that is directly related to reactor efficiency and safety. During the reactor operation, all sorts of microstructure defects will be generated by neutron irradiation and significantly reduce the thermal conductivity of fuels. Currently, experimental efforts to capture such thermal conductivity degradation is primarily through post-irradiation-examination (PIE). It has been speculated that point defects may anneal or cluster into larger scale defects prior to PIE, making the ex-situ measured properties different from the ones measured in-situ. Here we present the latest testing results of a fiber-based photothermal radiometry instrument that enables in situ thermal conductivity measurements of nuclear fuels. The performance and survivability of the instrument is tested at MIT research reactor. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, |