| About this Abstract |
| Meeting |
2025 TMS Annual Meeting & Exhibition
|
| Symposium
|
Microstructural, Mechanical, and Chemical Behavior of Solid Nuclear Fuel and Fuel-Cladding Interface II
|
| Presentation Title |
Methods of Implmentation and Sequestration of Iodine in UO2 Fuels |
| Author(s) |
James Edwin Portwin, Patrick Burr, Jessica Veliscek Carolan, Edward Obbard |
| On-Site Speaker (Planned) |
James Edwin Portwin |
| Abstract Scope |
Stress corrosion cracking (SCC) of zirconium cladding from corrosive iodine and pellet cladding interactions is a potentially life-limiting phenomenon for nuclear fuel. Current commercial reactors mitigate SCC through strict operating conditions however, SCC may become life-limiting for fuel in load-following applications, particularly for SMRs, which may require flexible operation. We investigate the possibility of trapping iodine within secondary phases of fuel pellets to reduce cladding interaction. Secondary phases are introduced by doping UO2 fuel with metal oxides, that have a high iodine bonding affinity, through an external gelation technique. We compare the effectiveness of Ca, Mg and Ba as dopants to produce iodine-trapping secondary phases. Results indicate that iodine can be added to a UO2 matrix in small quantities; iodine begins to volatilise at 650ºC during pellet sintering. Alternative methods for sintering, such as spark plasma sintering, or alternative iodine implementation techniques such as iodine diffusion, appear a promising solution. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Ceramics, Characterization |