| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Materials and Chemistry for Molten Salt Systems
|
| Presentation Title |
Microstructural Characterization of Grain Boundaries in Hastelloy N Corroded in Molten FLiBe Salt under Neutron Irradiation |
| Author(s) |
Guiqiu Tony Zheng, David Carpenter |
| On-Site Speaker (Planned) |
Guiqiu Tony Zheng |
| Abstract Scope |
The grain boundary (GB) of structural alloys plays an important role in the evaluation of corrosion resistance, radiation tolerance, thermal stability, and mechanical strength during their applications in extreme environments such as molten salt reactors. The degradation of GB strength induced by molten salt corrosion and neutron irradiation is one of the critical factors causing intergranular cracking of structural alloys, which dramatically shortens the service life of reactors. Hastelloy N and 2LiF-BeF2 (FLiBe) are being considered as the primary structural alloy and coolant for fluoride salt-cooled high-temperature reactors (FHRs). To evaluate the performance of Hastelloy N in simulated FHRs environment, Hastelloy N coupons were irradiated in molten FLiBe salt in both nickel-lined and graphite crucibles in the MIT Research Reactor at 700°C for 1000 hours. In this study the GB microstructure and microchemistry of irradiated Hastelloy N were characterized using the state-of-the-art instruments at the Idaho National Laboratory. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Characterization, Copper / Nickel / Cobalt |