| About this Abstract |
| Meeting |
2021 TMS Annual Meeting & Exhibition
|
| Symposium
|
Mechanical Behavior of Nuclear Reactor Components
|
| Presentation Title |
Mechanical Characterization of Neutron Irradiated HT-9 Heats (ORNL, LANL and EBR II) at LWR and Fast Reactor Relevant Temperatures |
| Author(s) |
Ramprashad Prabhakaran, Mychailo Toloczko, Kumar Sridharan |
| On-Site Speaker (Planned) |
Ramprashad Prabhakaran |
| Abstract Scope |
9-12 weight% ferritic-martensitic steels 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, the extreme hardening and low fracture toughness that occur at irradiation temperatures below 430°C is a serious issue. To address this concern, systematic investigations on the mechanical behavior and microstructure of HT-9 with slight variations in chemical composition and heat treatment are needed over a wide range of doses and temperatures to better understand the source of hardening. Mechanical characterization was performed on three HT-9 heats with different processing conditions irradiated to 3 dpa and 6 dpa (Advanced Test Reactor, Idaho) at 291°C, 360°C and 431°C to understand the effects of radiation damage, and to provide insight on desirable HT-9 processing conditions. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Nuclear Materials, Mechanical Properties, Environmental Effects |