About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Effect of Neutron Irradiation on HT-9 at LWR and Fast Reactor Relevant Temperatures |
| Author(s) |
Ramprashad Prabhakaran, Eda Aydogan, Mukesh Bachhav, Indrajit Charit, Kumar Sridharan, Stuart Maloy |
| On-Site Speaker (Planned) |
Ramprashad Prabhakaran |
| Abstract Scope |
Ferritic-martensitic steels containing 9-12 weight% Cr, such as HT-9, are being considered as candidate structural materials for fast, advanced LWR, and fusion reactors due to their excellent resistance to radiation-induced void swelling, good irradiation creep properties, microstructural stability, and thermal conductivity. However, hardening, and associated embrittlement effects at irradiation temperatures below 430°C warrant further study. To further evaluate this concern, systematic investigations on the mechanical behavior and microstructure of HT-9 with slight variations in composition and heat treatment are needed over a range of doses and temperatures to better understand the sources of hardening. Mechanical (microhardness and tensile testing) and microstructural (SEM, EBSD, TEM and APT) characterization was performed on HT-9 heats irradiated at different temperatures (241-469°C) and doses (3-8 dpa) in the Advanced Test Reactor (Idaho Falls, USA) to understand the effects of radiation damage, and to obtain processing-structure-properties-temperature-dose correlations. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Environmental Effects |