Coated Zirconium Alloy Fuel Rod Cladding for Accident Tolerance

涂层锆合金燃料棒包壳可耐受事故

• 批准号: 2648419
• 金额: --
• 依托单位: University of Manchester
• 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: 未结题
• 来源: https://gtr.ukri.org/projects?ref=studentship-2648419
• 关键词: Coated; Zirconium; Alloy; Fuel; Rod

Following the 2011 Great East Japan Earthquake, resulting tsunami, and subsequent damage to the Fukushima Daiichi nuclear power plant complex, enhancing the accident tolerance of PWRs became a topic of serious discussion. The safety of the nuclear power reactors has always been a top priority for operators and continual improvement of technology, including advanced materials and nuclear fuels, remains central to the industry's success. Decades of research combined with continual operation have produced steady advancements in technology and have yielded an extensive base of data, experience, and knowledge on pressure water reactor (PWR) fuel performance under both normal and accident conditions. Modern light water reactors (LWRs) are based on mature technology and have an excellent safety and operational record. Since the current UO2 - zirconium alloy fuel system meets all performance and safety requirements the goal of accident tolerant fuel (ATF) development is to identify alternative fuel system technologies to further enhance the safety. A leading solution proposed for ATF is the addition of a chromium coating to existing zirconium alloy cladding, further enhancing performance while building on existing knowledge. The aim of this project is to gain a better understanding of the comparative benefits of different methods of producing Cr coatings on Zr alloy cladding, in terms of the mechanical performance of this ATF cladding particularly at elevated temperatures. The project is jointly supported by Westinghouse (fuel vendor) and EDF (operator), based primarily in Manchester but will include the opportunity to perform experiments at EDF's experimental facility in Les Renardières, France. It is also part of MIDAS program, enabling interaction with a wide range of researchers working on related projects.

2011年东日本大地震引发海啸，福岛第一核电站受损，提高压水堆的事故容忍度成为人们严肃讨论的话题。核电反应堆的安全一直是运营商的首要任务，技术的持续改进，包括先进材料和核燃料，仍然是该行业成功的核心。数十年的研究与持续运行相结合，已经产生了技术的稳步进步，并产生了关于正常和事故条件下压水反应堆（PWR）燃料性能的广泛数据、经验和知识基础。现代轻水堆（LWRs）技术成熟，具有良好的安全和运行记录。由于目前的UO2 -锆合金燃料系统满足所有性能和安全要求，因此开发事故容忍燃料（ATF）的目标是确定替代燃料系统技术，以进一步提高安全性。针对ATF提出的一个领先解决方案是在现有的锆合金包层上添加铬涂层，在现有知识的基础上进一步提高性能。该项目的目的是为了更好地了解在Zr合金覆层上生产Cr涂层的不同方法的相对优势，特别是在高温下，这种ATF覆层的机械性能。该项目由Westinghouse（燃料供应商）和EDF（运营商）联合支持，主要位于曼彻斯特，但将有机会在法国Les renardiires的EDF实验设施进行实验。它也是MIDAS计划的一部分，可以与从事相关项目的广泛研究人员进行互动。