Zirconium alloys for high burn-up fuel in current and advanced light water-cooled reactors

当前和先进的轻型水冷反应堆中用于高燃耗燃料的锆合金

基本信息

批准号：
EP/E036384/1
负责人：
Chris Grovenor
金额：
$ 78.93万
依托单位：
University of Oxford
依托单位国家：
英国
项目类别：
Research Grant
财政年份：
2007
资助国家：
英国
起止时间：
2007 至无数据
项目状态：
已结题

来源：
https://gtr.ukri.org/projects?ref=EP%2FE036384%2F1
关键词：
Zirconium alloys burn up fuel

项目摘要

In order to improve the efficiency of modern nuclear reactors, reduce operating costs and minimise nuclear waste the fuel manufacturers together with plant operators and nuclear waste agencies are trying to develop fuel assemblies, which can operate for substantially longer times than what is currently achieved. Since Uranium-enrichment technology has progressed significantly in the last two decades it is now the fuel cladding material that limits the level of energy produced from a fuel assembly (termed burn-up by the nuclear industry). Increasing the so-called burn-up of fuel assemblies will improve the fuel economy/fuel usage of civil nuclear reactors, extend refuelling cycles (i.e. reduce the number of shutdowns for refuelling the reactor), and hence reduce the operating costs and nuclear waste. In modern nuclear reactors fuel cladding is based on zirconium alloys due to their good performance in the environment of water-cooled reactors and their transparency to neutrons. The time the cladding material can operate in such an environment (and therefore the level of energy that can be produced from a fuel assembly) is proportional to the corrosion properties. Longer lasting cladding material would require zirconium alloys with a more protective oxide layer, which would avoid any accelerated corrosion, breakaway of the oxide layer and protect against hydrogen pick-up. To date, any development in this area has been purely empirical and has not resulted in the required step change, which would allow operating the fuel assemblies to the desired burn-up. The scientific basis of this application is to address these issues by studying the influence and inter-relationships of all relevant microstructural features, local stresses, electronic defects in the oxide, in both commercial and model alloys when corrosion tested in an autoclave environment. This requires the project team to use the latest generation of analytical techniques in a coherent, interdisciplinary program. In addition our industrial partners provide access to additional specialist facilities such as autoclaves or melting facilities to produce model alloys. The key theme is to develop a mechanistic understanding of the corrosion process to enable the development of physically-based models, which will enable the design and full exploitation of alloys optimized to delay breakaway oxidation and oxidation growth. The research will be undertaken by a multi-university team, encouraging PhD students and post-doctoral research associates to form a core group of researchers who work together to exploit world-class facilities from different institutions.

为了提高现代核反应堆的效率，降低运营成本并最大限度地减少核废料，燃料制造商与工厂运营商和核废料机构正在努力开发燃料组件，其运行时间比目前实现的时间要长得多。由于铀浓缩技术在过去二十年中取得了显着进步，现在限制燃料组件产生的能量水平的燃料包壳材料（核工业称为燃耗）。增加燃料组件的燃耗将提高民用核反应堆的燃料经济性/燃料使用率，延长换料周期（即减少反应堆换料停机次数），从而减少运营成本和核废料。在现代核反应堆中，燃料包壳以锆合金为基础，因为它们在水冷反应堆环境中具有良好的性能，并且对中子具有透明性。包壳材料可以在这种环境中运行的时间（以及因此燃料组件可以产生的能量水平）与腐蚀特性成正比。更持久的包覆材料需要具有更具保护性的氧化层的锆合金，这将避免任何加速腐蚀、氧化层的破裂并防止氢气吸收。迄今为止，该领域的任何发展都纯粹是经验性的，并没有导致所需的阶跃变化，而这将允许燃料组件运行到所需的燃耗。该应用的科学基础是通过研究在高压釜环境中进行腐蚀测试时商用合金和模型合金中所有相关微观结构特征、局部应力、氧化物中的电子缺陷的影响和相互关系来解决这些问题。这要求项目团队在连贯的跨学科项目中使用最新一代的分析技术。此外，我们的工业合作伙伴还提供额外的专业设施，例如高压釜或熔化设施来生产模型合金。关键主题是建立对腐蚀过程的机械理解，以开发基于物理的模型，这将有助于设计和充分利用经过优化的合金，以延迟断裂氧化和氧化生长。该研究将由多所大学团队进行，鼓励博士生和博士后研究员组成核心研究小组，共同利用不同机构的世界一流设施。