About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Investigation of Nano-γ′ (Ni₃Al) for Enhanced Irradiation Tolerance in Advanced Ni-Based Alloys for Chloride MSRs |
| Author(s) |
Adrien Delagnes, Romane Buisson, Jacques Perrin Toinin, Sylvie Doriot, Joël Ribis, Yann de Carlan |
| On-Site Speaker (Planned) |
Adrien Delagnes |
| Abstract Scope |
Molten Salt Reactors (MSRs) are advanced fourth-generation systems offering intrinsic safety and efficient actinide recycling. Operating between 500-750°C with molten chlorides salts as both fuel and coolant, they require structural materials with excellent high-temperature strength, irradiation tolerance, and corrosion resistance.
NiMolloy-202 is a new nickel-based alloy that was specifically developed at CEA for use in MSRs. Free of chromium and iron, and containing 20 wt.% molybdenum, NiMolloy-202 is strengthened by a high density of nanometric γ′ (Ni₃Al) precipitates, which enhance its mechanical performance, irradiation resistance, and helium embrittlement. TEM, APT and in situ SAXS analyses confirmed a fine and stable γ′ dispersion.
This presentation aims to demonstrate which microstructures are targeted for MSRs, and explain how thermomechanical treatments can control precipitation and influence both the mechanical properties and the dense nanometric distribution of γ'.
The results are analyzed and discussed with respect to the objectives of developing new grades for MSRs. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Characterization, Nuclear Materials, Mechanical Properties |