About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Ceramics and Ceramic-Based Composites for Nuclear Applications III
|
| Presentation Title |
Can studies on specific fuels from past irradiations be valorised for future SMR/AMR |
| Author(s) |
Thierry Wiss, Jaroslava Pravdova, Christophe Nourry, Vincenzo V. Rondinella |
| On-Site Speaker (Planned) |
Thierry Wiss |
| Abstract Scope |
Over the last 60 years, JRC Karlsruhe has been at the forefront to perform post-irradiation examinations of nuclear fuels. JRC-KA has analysed a very broad spectrum of fuels irradiated in research, light water and fast reactors covering among others, UOX and MOX from test and commercial irradiations, oxides, carbides, nitrides, metal alloys irradiated in a fast neutronic spectrum, and TRISO coated particle fuel for high-temperature reactors. The fuels tested addressed open and closed cycle applications, including fuel incorporating minor actinides for transmutation safety studies.
Some of these samples may still possess high scientific and technological value for research and development in the field of advanced nuclear technologies, including Advanced Modular Reactors (AMR) and Small Modular Reactors (SMR). Examples will be given of relevant studies on the safety of fuel compounds during irradiation and on the safety of the corresponding spent fuel management. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Other, Nuclear Materials, Characterization |