About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
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Symposium
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Mechanical Behavior of Nuclear Reactor Materials and Components III
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Presentation Title |
Mechanical and Microstructural Characterization of Neutron Irradiated HT-9 Heats at LWR and Fast Reactor Relevant Temperatures |
Author(s) |
Ramprashad Prabhakaran, Indrajit Charit, Dan Edwards, Mychailo Toloczko, Stuart Maloy, Kumar Sridharan |
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 and microstructural characterization were performed on three heats of HT-9 (ORNL, LANL and EBR II) with different processing conditions irradiated to 3-8 dpa in the Advanced Test Reactor at 291°C, 360°C and 431°C to understand the effects of radiation damage, and to provide insight on desirable processing conditions. |
Proceedings Inclusion? |
Planned: |
Keywords |
Mechanical Properties, Nuclear Materials, Environmental Effects |