|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Radiation Effects on HT9 Tempered Martensitic Steels as a Function of Initial Dislocation Density
||Eda Aydogan, Stuart Maloy, Yongqiang Wang
|On-Site Speaker (Planned)
Tempered martensitic steels are excellent candidates for next generation advanced nuclear applications for fusion and fission reactors. The initial microstructure has a significant effect on radiation response of the materials. There is a general perception that cold working or an increase in the dislocation density suppresses radiation induced swelling. However, previous research has shown that cold working might either reduce or increase swelling, besides having no effect on it. In this study, effect of deformation amount and states on radiation response of the materials have been investigated in HT9 F/M steels. HT-9 materials were deformed to 10%, 30% and 50% both uniaxially (plane strain) and by severe plastic deformation (shear). The materials were irradiated with 5 MeV iron ions at 450 șC. Microstructural characterization and nanohardness testing will be shown on those materials before and after irradiation and compared to previous results on other alloys.
||Planned: Supplemental Proceedings volume