| About this Abstract |
| Meeting |
2024 TMS Annual Meeting & Exhibition
|
| Symposium
|
Irradiation Testing: Facilities, Capabilities, and Experimental Designs
|
| Presentation Title |
Nuclear Fuel Salt Irradiation and Post-irradiation Processing Capabilities at The Ohio State University Research Reactor |
| Author(s) |
Matt Van Zeil, Andrew Kauffman, Praneeth Kandlakunta, Kevin Herminghuysen, Susan White, Lei Raymond Cao |
| On-Site Speaker (Planned) |
Matt Van Zeil |
| Abstract Scope |
The Ohio State University Research Reactor (OSURR) has established irradiation capabilities for fuel salt irradiation and post-irradiation handling and analysis. Extensive safety analyses, including considerations for fission gas and fission product escape, heat deposition from gamma heating, neutron and fission energy deposition into the salt, have equipped the OSURR with the necessary glove box facilities and safety procedures to handle small-scale irradiated fuel salt samples. In the most recent study, a 6.065 g sample of MgCl-KCl-UCl3 salt mixture containing 1.21 mg of U-235 was irradiated in-core at the 500-kW Ohio State University Research Reactor. The resulting neutron fluence was 4.0x10^16 cm^2, equivalent to a fuel burn-up of 0.035 MWd/MTU (3.5x10^-5 GWd/MTU). During irradiation, the fuel salt was in a solid format and later melted for subsequent sampling and measurement. Over a 42-day post-irradiation period, gamma spectra were acquired to analyze fission products. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Other, Other |