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

小型模块化反应堆(SMR)有不同的用途，这取决于它们的大小、设计和能量范围。例如，在安大略省和萨斯喀彻温省，决定部署沸水反应堆技术来发电，而阿尔伯塔省可能会使用非常高温的气冷反应堆技术来提取自然资源或生产低碳氢气。将用于SMRS结构的金属合金将暴露在高温下，同时承载机械载荷并受到裂变产生的中子的照射。这将导致合金的退化，潜在地降低反应堆部件的有效寿命。本研究致力于发展一种先进的数值模型和现场实验技术来模拟辐照和热机械载荷对SMR候选金属合金性能的影响。数值模型将根据实验数据集进行验证，这些数据集将从纳米到宏观尺度进行测量。预计该模型在开发时将有助于确定候选金属合金的安全裕度，从而降低过度试错试验的成本。此外，高温下测量的实验数据集将有助于对候选金属合金的性能做出明智的决定，并了解导致它们退化的潜在机制。

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.