Liquid lithium corrosion for nuclear fusion

核聚变的液态锂腐蚀

• 批准号: 2888322
• 金额: --
• 依托单位: University of Oxford
• 依托单位国家: 英国
• 项目类别: Studentship
• 财政年份: 2023
• 资助国家: 英国
• 起止时间: 2023 至 无数据
• 项目状态: 未结题
• 来源: https://gtr.ukri.org/projects?ref=studentship-2888322
• 关键词: Liquid; lithium; corrosion; nuclear; fusion

The blanket module of the fusion devices of the future is likely to have a coolant, that not only cools the reactor, but breeds tritium, the fuel that is used within the plasma. This can either be PbLi eutectic or pure lithium. PbLi has been extensively studied due to its ability to multiply neutrons (Pb) and breed tritium (Li). However PbLi does not breed as much tritium as a pure lithium. Whilst there has been much corrosion testing using PbLi there has been much less using liquid lithium. Reports form the 1970's suggest refractory metals have better compatibility in liquid lithium than other metals and more recent work in Japan suggest erbium oxide maybe be a potential coating. We have developed a bespoke liquid lithium testing rig in Oxford to allow testing at a range of temperatures in static Li and PbLi. To understand the tolerance of these coatings with the environment, preliminary tests in Li have been performed to understand the chemical compatibility. However, tests to understand the synergistic effects of liquid lithium and irradiation are difficulty and costly as there is a lack of testing equipment globally. So, tests in Li and irradiation environments are usually done subsequently, rather than concurrently.This project will use a combination of proton irradiation at the National Ion Beam Centre and PbLi and Li corrosion at the new established Oxford testing facility to understand synergistic effects that may occur under these conditions.Characterisation of the degradation process will use analytical electron microscopy including STEM-EDX, SEM-TKD and FIB-SEM tomography. Adhesive properties of the coatings will be measured using scratch testing methods developed in Oxford to understand interfacial failure mechanisms. The results from the microstructural and mechanical characterisation will be used to either engineer the alloy chemistry or coating combinations to improve the resistance to degradation and decohesion. Further development of the corrosion facilities as part of the project will include integration of the stirring within the liquid lithium crucible and oxygen level sensors. There is likely to be industrial support from a SME to this project.

未来聚变装置的包层模块很可能有一种冷却剂，不仅可以冷却反应堆，还可以产生氚，即在等离子体中使用的燃料。这可以是PbLi共晶或纯锂。PbLi由于其增殖中子（Pb）和增殖氚（Li）的能力而被广泛研究。然而，PbLi不会像纯锂那样产生那么多的氚。虽然使用铅锂进行了大量腐蚀测试，但使用液态锂的测试却少得多。20世纪70年代的报告表明，难熔金属在液体锂中比其他金属具有更好的相容性，日本最近的研究表明，氧化铒可能是一种潜在的涂层。我们在牛津开发了一个定制的液态锂测试装置，可以在静态锂和PbLi的温度范围内进行测试。为了了解这些涂层对环境的耐受性，在Li进行了初步测试，以了解化学相容性。然而，由于全球缺乏测试设备，因此了解液体锂和辐照的协同效应的测试是困难和昂贵的。因此，在锂和辐照环境中的测试通常是随后进行的，而不是同时进行的。该项目将使用国家离子束中心的质子辐照和新建立的牛津测试设施的PbLi和Li腐蚀相结合，以了解在这些条件下可能发生的协同效应。降解过程的表征将使用分析电子显微镜，包括STEM-EDX，SEM-TKD和FIB-SEM断层扫描。涂层的粘合性能将使用牛津开发的划痕试验方法进行测量，以了解界面失效机制。微观结构和机械表征的结果将用于设计合金化学或涂层组合，以提高抗降解和抗脱粘性。作为该项目的一部分，腐蚀设施的进一步开发将包括在液态锂坩埚内集成搅拌和氧含量传感器。中小企业很可能对这一项目提供工业支持。