Deciphering Spent Nuclear Fuel Complex Materials Using Model System and High-Resolution Studies
- Datum: 05.02.2026
- Uhrzeit: 13:15
- Vortragende(r): Gabriel Murphy
- Forschungszentrum Juelich
- Ort: MPI CPfS
- Raum: Seminarraum 1 + 2
- Gastgeber: Dr. E. Svanidze
Precisely and effectively tackling the challenge of spent nuclear fuel materials science requires a combination of challenging direct studies of irradiated specimens with model system studies of synthesized representative materials. The synergy of these methods, combined with high resolution measurement and theory, enables excellent and relevant understanding unto the behaviour of spent nuclear fuel materials supporting both regulators, implementors whilst generating fundamental radiochemical knowledge. This presentation will subsequently highlight and discuss fundamental experimentally driven efforts to understand and decipher the complexity of (1) Mixed-Oxide (MOX) high burn up spent fuel, used significantly in Germany and Europe, (2) Accident tolerant nuclear fuel (ATF) redox and microstructural performance, seeing rapid take off in north American and French power reactor units and finally (3) potential future generation IV uranium nitride based spent fuel inventories, seen as the successor to UO2.