Microstructure-informed modeling and experimentation of nuclear materials: coupled temperature and irradiation effects

点击翻译按钮获取中文摘要

There are different uses for small modular reactors (SMR), depending on their size, design, and energy range. For example, in the provinces of Ontario and Saskatchewan, it is decided to deploy the boiling water reactor technology to produce electricity, while the very high temperature gas cooled reactor technology might be used in Alberta for natural resources extraction or low-carbon hydrogen generation. The metal alloys that will be used in the structure of SMRs will be exposed to high temperatures while carrying mechanical loads and being irradiated with neutrons from fission. This will lead to the degradation of the alloys, potentially reducing the effective lifetime of reactors' components. This research focuses on the development of an advanced numerical model and in-situ experimental techniques for simulating the combined effects of irradiation and thermomechanical loads on the performance of candidate metal alloys for SMRs. The numerical model will be validated against the experimental data sets that will be measured from nano to macro-scales. It is expected that when it is developed, the model helps determine the safety margins of candidate metal alloys, hence reduce the cost of excessive trial-and-error experimentations. Further, the measured experimental data sets at elevated temperatures will help make informed decision regarding the performance of candidate metal alloys, and understand the underlying mechanisms that contribute to their degradation.