Ceramic Coatings for Clad (The C^3 Project): Advanced Accident-Tolerant Ceramic Coatings for Zr-alloy Cladding

用于熔覆层的陶瓷涂层（C^3 项目）：用于 Zr 合金熔覆层的高级耐事故陶瓷涂层

基本信息

批准号：
EP/K039237/1
负责人：
Karl Whittle
金额：
$ 136.99万
依托单位：
University of Sheffield
依托单位国家：
英国
项目类别：
Research Grant
财政年份：
2013
资助国家：
英国
起止时间：
2013 至无数据
项目状态：
已结题

来源：
https://gtr.ukri.org/projects?ref=EP%2FK039237%2F1
关键词：
Ceramic Coatings Clad Project Advanced

项目摘要

Enhancing the safety of nuclear fuel is an important component in the continued use, and expansion, of nuclear power. One area where safety can be enhanced is enhancing the cladding around the nuclear fuel. Such a coating will enhance further the long term stability of the fuel under normal reactor operation, whilst at the same provide an extra level of insurance should an incident similar to that in Fukushima happen. These new coatings will provide a barrier between the Zircalloy cladding and air/water, which will help to prevent the formation of hydrogen gas from steam formed when there is a loss of coolant accident (LOCA), i.e. the process that happened at Fukushima Daichi, in March 2011.Using the combined expertise/knowledge from within the UK and US a collaborative research team has been put together to develop such coatings. Two options will be addressed one based on using oxide, such as zirconia, whilst a second will be based on ternary carbide/nitride based materials, such as MAX phases. M(n+1)AX(n) phases have previously been shown to not only recover rapidly from radiation damage, but also excellent thermal/corrosion properties making them ideal for this application. For the development of new coatings to be used in the current, and future, nuclear reactor fleet, new coatings must be prepared, and examined for stability, under a range of reactor conditions. The experimental programme will address issues such as the preparation of the coating, stability of bonding between coating and fuel, the effects of radiation damage on the interface, and how the enhanced coating increases stability of the fuel to both high temperatures/pressures experienced within a fission core. These experiments will also be used to validate simulations of corrosion, providing a means by which simulations can be reliably used. One final assessment of the coatings once tested, is how they behave under conditions that model a LOCA event. The results from this work will be used in developing technologies for existing and future reactor technologies.

增强核燃料的安全是核能的持续使用和扩展的重要组成部分。可以增强安全性的一个区域是增强核燃料周围的覆层。这样的涂层将进一步增强正常反应堆操作下燃料的长期稳定性，而在同一事件发生类似的事件中，同一涂层在同一情况下提供了额外的保险。这些新涂层将在锆石覆盖层和空气/水之间提供障碍，这将有助于防止在冷却液事故损失（LOCA）（即发生在福岛Daichi）中，从而形成氢气，从而形成氢气。在2011年3月。使用英国境内和美国的联合专业知识/知识，一支合作研究团队已经组装在一起来开发此类涂料。将根据使用氧化物（例如氧化锆虫）来解决两个选项，而第二个将基于三元碳化物/氮化物材料，例如最大相。 M（n+1）AX（N）阶段先前已被证明不仅从辐射损伤中迅速恢复，而且还可以恢复出色的热/腐蚀特性，使其非常适合这种应用。为了开发新的涂料在当前和未来的核反应堆机队中，必须在一系列反应堆条件下准备并检查新涂层并进行稳定性检查。实验计划将解决诸如制备涂层，涂层和燃料之间粘结的稳定性，辐射损伤对界面的影响以及增强涂层如何提高燃料对两种高温/压力的稳定性的影响裂变芯。这些实验还将用于验证腐蚀的模拟，提供一种可以可靠地使用模拟的方法。一旦测试的涂料的最终评估是它们在模拟LOCA事件的条件下的表现。这项工作的结果将用于开发现有反应堆技术的技术。