MIDAS - Mechanistic understanding of Irradiation Damage in fuel Assemblies

MIDAS - 燃料组件中辐照损伤的机理理解

• 批准号: EP/S01702X/1
• 负责人: Michael Preuss
• 金额: $ 920.82万
• 依托单位: University of Manchester
• 依托单位国家: 英国
• 项目类别: Research Grant
• 财政年份: 2019
• 资助国家: 英国
• 起止时间: 2019 至 无数据
• 项目状态: 未结题
• 来源: https://gtr.ukri.org/projects?ref=EP%2FS01702X%2F1
• 关键词: MIDAS; Mechanistic; understanding; Irradiation; Damage

In order to meet the UK's carbon reduction targets, and achieve an energy mix that produces less CO2, we must continue to investigate ways in which to make nuclear power cleaner, cheaper and safer. At the same time, as new reactors such as Hinkley Point C are built, the UK needs to develop the work force who will operate, regulate and solve technical problems in civil nuclear power, in order to capitalise on our investment in nuclear energy. Important in this respect is that the UK currently operates mainly old advanced gas-cooled reactors, fundamentally different from the next fleet of UK nuclear power stations, which will be light-water reactors. Key to this change, in terms of this research project, is that Zirconium is a preferred fuel cladding material in LWRs.A major part of a nuclear reactor is the fuel assembly - the structure that encapsulates the highly radioactive nuclear fuel. Understanding the performance of the materials used to make these assemblies is critical for safe, efficient operation, and they must be able to maintain their structure during normal operation, handling and storage, as well as survive in the unlikely event of an accident, when they become crucial in preventing the escape of radioactive materials. Because of the need to operate nuclear reactors as safely as possible, fuel is often removed well before it is spent, as we currently do not know enough about fuel assembly materials, so must adopt a highly cautious, safety-first approach. This does mean, however, that it is more costly to run a reactor, as assemblies must be replaced well before all the fuel is consumed, and this also means the assembly then - prematurely - becomes additional nuclear waste, which must be safely handed and stored, at further high cost.By gaining greater understanding of how assembly materials perform when irradiated, we will be able to make more accurate safety cases, which will mean that fuel assemblies can be used for longer periods without additional risk. Such knowledge will enable the UK to operate the next generation of reactors far more efficiently, significantly reducing the cost of nuclear power. This is particularly important now, given that the UK is going to have light-water, instead of advanced gas-cooled, reactors, and with it the fuel assembly and its material will change very fundamentally.This research effort will also significantly benefit other countries using nuclear energy, which will establish the UK as a centre of expertise in the area. This will further attract inward investment in research and development in the UK, creating future wealth and employment alongside cleaner energy.A second key theme of the project will be to explore the use of zirconium alloys in critical components for future fusion reactors. The UK has a leading position in defining the materials that will be chosen for the ITER and DEMO international fusion projects, and this theme will contribute to maintaining the UK's reputation as a centre of excellence in fusion research.

为了实现英国的碳减排目标，并实现减少二氧化碳排放的能源结构，我们必须继续研究如何使核电更清洁、更便宜和更安全。与此同时，随着欣克利角C等新反应堆的建成，英国需要培养能够操作、监管和解决民用核电技术问题的劳动力，以便从我们对核能的投资中获益。在这方面重要的是，英国目前主要运行旧的先进气冷反应堆，与英国下一代核电站（即轻水反应堆）有着根本的不同。就本研究项目而言，这一变化的关键在于锆是轻水堆中首选的燃料包壳材料。核反应堆的主要部分是燃料组件，即封装高放射性核燃料的结构。了解用于制造这些组件的材料的性能对于安全、高效的操作至关重要，并且它们必须能够在正常操作、搬运和存储期间保持其结构，并且能够在不太可能发生的事故中幸存下来。对于防止放射性物质泄漏至关重要。由于需要尽可能安全地运行核反应堆，燃料通常在耗尽之前就被移除，因为我们目前对燃料组件材料了解不够，因此必须采取高度谨慎、安全第一的方法。然而，这确实意味着运行反应堆的成本更高，因为必须在所有燃料耗尽之前更换组件，这也意味着组件然后过早地变成额外的核废料，必须安全处理和处理。通过更好地了解组装材料在辐照时的性能，我们将能够做出更准确的安全案例，这意味着燃料组件可以使用更长时间，而不会产生额外的风险。这些知识将使英国能够更有效地运行下一代反应堆，从而显着降低核电成本。鉴于英国将拥有轻水反应堆，而不是先进的气冷反应堆，这一点现在尤为重要，并且燃料组件及其材料将发生根本性的变化。这项研究工作也将使其他国家受益匪浅使用核能，这将使英国成为该领域的专业中心。这将进一步吸引英国的研发投资，与清洁能源一起创造未来的财富和就业。该项目的第二个关键主题将是探索锆合金在未来聚变反应堆关键部件中的使用。英国在定义 ITER 和 DEMO 国际聚变项目所选材料方面处于领先地位，这一主题将有助于维护英国作为聚变研究卓越中心的声誉。

项目成果

Predicting crack patterns in SiC-based cladding for LWR applications using peridynamics

使用近场动力学预测轻水堆应用中碳化硅包壳的裂纹模式

• DOI: 10.1016/j.prostr.2020.10.125
• 发表时间: 2020
• 期刊: Procedia Structural Integrity
• 作者: Bamgboye A

Zirconium in the Nuclear Industry: 19th International Symposium

核工业中的锆：第十九届国际研讨会

• DOI: 10.1520/stp162220190016
• 发表时间: 2021
• 作者: Liu J

Effect of Temperature and Hydrogen Concentration on the Threshold Stress Intensity Factor of Radial Delayed Hydride Cracking in Fuel Cladding

• DOI: 10.1016/j.jnucmat.2022.153737
• 发表时间: 2022-04
• 期刊: Journal of Nuclear Materials
• 影响因子: 3.1
• 作者: A. Colldeweih;J. Bertsch

Quantifying cracking and strain localisation in a cold spray chromium coating on a zirconium alloy substrate under tensile loading at room temperature

• DOI: 10.1016/j.jnucmat.2024.154899
• 发表时间: 2024-01
• 期刊: Journal of Nuclear Materials
• 影响因子: 3.1
• 作者: Ioannis Alakiozidis;Callum Hunt;R. Thomas;D. Lunt;Albert D. Smith;Mia Maric;Zaheen Shah;A. Ambard;Philipp Frankel

Zirconium hydride phase mapping in Zircaloy-2 cladding after delayed hydride cracking

• DOI: 10.1016/j.mtla.2023.101689
• 发表时间: 2023-01
• 期刊: Materialia
• 影响因子: 3.4
• 作者: A. Colldeweih;M. Makowska;Omaima Tabai;D. F. Sanchez;J. Bertsch