Microscale to Macroscale Modelling of the Corrosion in Nuclear Systems

核系统腐蚀的微观到宏观建模

• 批准号: 2123347
• 金额: --
• 依托单位: University of Bristol
• 依托单位国家: 英国
• 项目类别: Studentship
• 财政年份: 2018
• 资助国家: 英国
• 起止时间: 2018 至 无数据
• 项目状态: 已结题
• 来源: https://gtr.ukri.org/projects?ref=studentship-2123347
• 关键词: Microscale; Macroscale; Modelling; Corrosion; Nuclear

The interaction of nuclear fuel and barrier material with water is a primary concern for the UK, whether Magnox, AGR, or exotic, whether in-operation, stored interim or long-term. Retrievals and relocation operations are imminent and new nuclear build presents the need to state our plans publicly up front. Any measurements/models that mitigate these risks and inform future decisions would be welcome. The principal aim to provide a testable predictive tool should directly impact the UK, informing decision making on spent fuel disposition and future material deployment. We plan to collaborate with current partners (CEA) and within the UK (Lancaster, Cambridge) to better understand the fundamental behaviour of water at the surface of spent fuel. We plan to develop FACSIMILE + COMSOL models in collaboration with NNL, moving towards real-world systems. We will then design experiments that mimic these idealised scenarios and test them. This method can cut across nuclear fission themes of cladding and fuel corrosion and even shed light on important mechanisms that may be at work in the corrosion of Tokamak fusion devices. Idealised samples will be synthesised, using the actinide thin film deposition system at the University of Bristol. We plan to use facilities such as the DCF and Surrey Ion Beam Centre to investigate radiation damage and we have a collaboration with the KURRI and CLADS facility in Japan, which will enable irradiation of thin film samples with high neutron fluxes. This project will bring the theorists and experimentalists together on a joint venture; retaining, building and developing knowledge-base for future generations.

核燃料和屏障材料与水的相互作用是英国主要关注的问题，无论是Magnox、AGR还是外来的，无论是在运行中、临时储存还是长期储存。回收和重新安置行动迫在眉睫，新的核建设提出了公开声明我们的计划的必要性。任何能够减轻这些风险并为未来决策提供信息的衡量标准/模型都是受欢迎的。提供一个可测试的预测工具的主要目标应直接影响英国，为乏燃料处置和未来材料部署的决策提供信息。我们计划与目前的合作伙伴（CEA）和英国（兰开斯特，剑桥）合作，以更好地了解乏燃料表面水的基本行为。我们计划与NNL合作开发FACSIMILE + COMSOL模型，向真实世界系统迈进。然后，我们将设计模拟这些理想化场景的实验并对其进行测试。这种方法可以跨越包壳和燃料腐蚀的核裂变主题，甚至阐明托卡马克聚变装置腐蚀中可能起作用的重要机制。理想化的样品将使用布里斯托大学的锕系元素薄膜沉积系统合成。我们计划使用DCF和萨里离子束中心等设施来调查辐射损伤，我们与日本的KURRI和CLADS设施合作，这将使薄膜样品具有高中子通量。该项目将使理论家和实验家共同参与一项合资企业;为后代保留、建立和发展知识基础。