|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Accelerated Materials Evaluation for Nuclear Application Utilizing Test Reactors, Ion Beam Facilities and Integrated Modeling
||High-dose Neutron Irradiation Induced Evolution of Mechanical Properties and Microstructure of Ferritic/Martensitic Steels
||Kun Wang, Kevin G Field, Chad M Parish, Josina W Geringer, Yutai Katoh
|On-Site Speaker (Planned)
Ferritic/martensitic (FM) steels are leading candidate structural materials for fusion reactors, targets of spallation systems and fuel cladding in fast reactors. FM steels exhibit excellent resistance to void swelling and creep and good balance of physical and mechanical properties. However, due to the lack of high flux neutron irradiation test reactor, the mechanical behavior of FM steels at high irradiation dose are still not well known.
ORNL 9Cr-2WVTa and Eurofer97 (Fe-9Cr) have been irradiated in the High Flux Isotope Reactor (HFIR) to a damage level of 42-64 displacements per atom (dpa) in a temperature range of 300-345 °C. Post-irradiation examination was completed including evaluation of post irradiation micro-hardness, tensile properties, and microstructures. In particular, microstructures were characterized, including irradiation induced dislocation loops, cavities, and precipitates using advanced analytical electron microscopy such as scanning transmission electron microscopy (STEM) equipped with super x-ray detector or energy-filtering transmission electron microscopy (EFTEM).
||Planned: Supplemental Proceedings volume