|About this Abstract
||2018 TMS Annual Meeting & Exhibition
||Materials and Fuels for the Current and Advanced Nuclear Reactors VII
||Neutron irradiation Induced Microstructures in Ferritic/Martensitic Steel HT9
||Ce Zheng, Djamel Kaoumi
|On-Site Speaker (Planned)
Ferritic/Martensitic (F/M) steel HT9 is considered as a promising candidate for structural and cladding applications in Generation IV reactors. The harsh service conditions in Generation IV reactors require that the microstructural response of candidate structural alloys to radiation be investigated and understood to qualify their performance in a nuclear environment. For this purpose, neutron irradiations of HT9 were carried out in BOR-60 reactor to 33 and 16.6 dpa at 360°C. TEM specimens were prepared by the Focus Ion Beam (FIB) lift-out method. The irradiated microstructures (dislocation loops and cavities) in neutron irradiated HT9 were characterized by conventional transmission electron microscopy (TEM) whereas the radiation induced precipitation (e.g. α’ and g phase) and segregation (RIP and RIS) in the same alloy were examined using the ChemiSTEM technique. The effect of irradiation dose on the irradiated microstructures as well as RIP & RIS is thus discussed.
||Planned: Supplemental Proceedings volume