Testing of Advanced Nanoparticle Dispersed Steels for Next Generation Reactors

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My research career is focused on the investigation of radiation effects of reactor materials and development of future nuclear materials. Oxide dispersion strengthened steels (ODS) are probably the most promising structural materials that could handle the tough challenges involved in the design of the next generation of nuclear reactors. Therefore we started an ODS program two years ago with support from my previous NSERC Discovery Grant at Queen's. In our proposal both martensitic and austenitic ODS steels will be investigated. Martensitic ODS steels are mainly based on Fe-9% Cr alloys, and austenitic ODS steels are based on 316 and 310 stainless steels. Our program targets the metallurgical processing advancement and comprehensive property testing of these materials over the next five years. I and my students will focus on the complete microstructure characterization and irradiation testing of the ODS steels we previously designed. The comprehensive investigation will provide a good understanding of (1) process induced microstructures, such as grain morphology, particle size and spatial distribution and chemical map of elements, which will give accurate feedback to the manufacturing group of our collaborators in China for further development, and (2) irradiation behaviour under ion irradiation, to simulate the neutron irradiation conditions found in reactors, with support of (3) molecular dynamics simulation of atomic displacement and defect clustering and (4) determine the correlation between irradiation properties and the designed microstructures. The above outlined research issues will highlight the importance of microstructure response on irradiation induced mechanical behaviours. The information learned from this research will expand our knowledge about how ODS steels perform under certain conditions, give us an understanding of their structural properties, and lead to formulations that could withstand the rigors of a nuclear environment. Results will provide useful ground for selection of materials that are more resist radiation damages which will guide the design of future materials. In addition, since ODS steels possess exceptional high-temperature creep*and corrosion and irradiation resistance they also have great potential*for use as structural materials for concentrated solar power plants,*jet engines, chemical reactors as well as for hydrogen production from*thermolysis of water. As a result, this research will lead to advancements in nuclear technologies and materials research, to the benefit of Ontario and all Canadians. The sharing of information and facilities featured in this research proposal will support and enhance current international collaborations. In addition, thanks to this proposal, we will provide a high level of HQP training to the next generation of researchers.