Aging of Inconel X-750 spacer material

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The purpose of this project is to develop an understanding of the embrittlement behaviour of one of the key mechanical components in a CANDU nuclear power reactor: the spacer, which is located between the calandria tube and the pressure tube. This project is aiming at evaluating radiation induced degradation of spacer material as well as developing a basic science understanding of irradiation damage in an industrially relevant Ni based alloy. The focus of this project will be to examine the effects of displacement damage using energetic ions (as an analogue to fast neutron irradiation), combined with the effect of helium. The short and long term results are directly applicable to understanding the effect of aging on the integrity of CANDU spacers. The techniques and analysis methods applied here to ion irradiated materials will help in the characterization and interpretation of measurements on neutron irradiated materials being studied at the Chalk River Laboratory (CRL) in parallel. The experimental results will also be used to validate molecular dynamic (MD) simulation models, to establish the intrinsic relationship between irradiation induced nano defects and its induced mechanical degradation. In addition, thanks to this project, we will provide a high level of HQP training for the new generation of nuclear engineers.