Understanding Radiation Damage in Zircaloy-4 for Current and Future Nuclear Applications

了解当前和未来核应用中 Zicaloy-4 的辐射损伤

• 批准号: 2445678
• 金额: --
• 依托单位: University of Huddersfield
• 依托单位国家: 英国
• 项目类别: Studentship
• 财政年份: 2020
• 资助国家: 英国
• 起止时间: 2020 至 无数据
• 项目状态: 已结题
• 来源: https://gtr.ukri.org/projects?ref=studentship-2445678
• 关键词: Understanding; Radiation; Damage; Zircaloy; Current

Zircaloy-4 is a Zr-based alloy of major importance for nuclear fuel cladding in pressurised water reactors. Under irradiation at high temperatures, it develops microstructural defects including dislocation loops and gas bubbles. Hydrides can also develop due to aqueous corrosion. Such defects can have significant effects on the performance of the material and hence needs to be accurately quantified for the continued use and future development of reactor technologies incorporating such alloys into their design. This PhD project will support a fledging collaboration with Rolls Royce (who will provide Zircaloy-4 samples) which has emerged from the Horizon 2020 "IL TROVATORE" project.

Zircloy-4 是一种锆基合金，对于压水反应堆中的核燃料包壳具有重要意义。在高温照射下，它会产生微观结构缺陷，包括位错环和气泡。由于水腐蚀也会产生氢化物。这些缺陷会对材料的性能产生重大影响，因此需要准确量化，以便继续使用和未来开发将此类合金纳入其设计的反应堆技术。该博士项目将支持与劳斯莱斯（劳斯莱斯将提供 Zircloy-4 样品）的初步合作，该合作是地平线 2020“IL TROVATORE”项目中出现的。