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Intermetallic Dispersion Strengthened 'IDS-Steels' for Generation IV Nuclear

Intermetallic Dispersion Strengthened 'IDS-Steels' for Generation IV Nuclear
用于第四代核电的金属间弥散强化“IDS-钢”
批准号:
EP/T016566/1
负责人:
Alexander Knowles
金额:
$80.14万
依托单位:
依托单位国家:
英国
项目类别:
Research Grant
财政年份:
2022
资助国家:
英国
项目状态:
未结题
起止时间:
2022 至 --

项目摘要

项目成果

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中文摘要
翻译
该计划将开发新一代抗蠕变金属间弥散强化‘IDS-钢’,能够承受第四代反应堆、先进模块化反应堆(AMR)和先进技术燃料(ATF)的苛刻操作要求。这个相互联系的英国-印度团队由来自伯明翰、班戈、曼彻斯特、IGCAR和BARC的研究人员组成,支持早期职业研究人员,以及双向研究和学术访问。为了满足英国和印度未来的能源需求和巴黎协议下的脱碳承诺,核能将是至关重要的。英国和印度都在开发未来的第四代核裂变技术,这种技术将减少核能的成本和废物产生,同时本质上是“安全的”。第四代反应堆的设计使用了先进的冷却剂,如熔融金属(如钠)、熔盐或气体冷却剂,这些冷却剂需要500-800摄氏度的高运行温度,这比目前的水冷反应堆要高得多,因此需要比目前使用的更高性能的先进结构材料。与目前的反应堆相比,正在考虑和开发各种先进材料来满足第四代反应堆及其更具侵蚀性的条件(冷却剂化学、温度和辐射损害)的需求。尽管取得了重大成功,但要达到第四代先进反应堆所需的性能平衡仍然面临重大挑战,而且继续需要开发新材料。一种显示出重大前景并开辟了一个新研究领域的材料是氧化物弥散强化(Ods)钢,它是在过去30年中开发的。然而,在商业规模的可制造性方面仍然存在挑战。在过去的十年里,先进的非核金属间化合物增强钢得到了迅速的发展,性能得到了极大的改善。这是由于材料建模方面的巨大改进,即原子尺度建模(DFT)和热力学数据库(CALPHAD),从而加速了合金的开发进程。在这项工作中,我们提出了一种新的方法,学习核消耗臭氧层物质钢,非核金属间化合物增强钢的成功,以及材料建模方面的进展。新一代抗蠕变的消耗臭氧层物质类似的“金属间弥散强化”“金属间弥散强化”钢将被开发出来,能够承受第四代反应堆的苛刻操作要求。英国和印度之间的双向知识交流是这项提议的核心部分,从而建立了超过赠款期限的长期联系。在整个一揽子工作中都强调了这一点,其中结合了双方的专业知识。这种紧密的联系将通过英国和印度之间每两年轮流访问1-2周来确保,包括嵌入研究人员在切除实验室的时间,英国每季度召开一次会议,包括与印度的电话会议,然后在一个开放的英国-印度资助结束研讨会上展示该项目的结果。
英文摘要
This programme will develop a new generation of creep-resistant Intermetallic Dispersion Strengthened 'IDS-steels', capable of withstanding the demanding operating requirements of Generation IV reactors, Advanced Modular Reactors (AMR), and Advanced Technology Fuels (ATF). The interlinked UK-India team comprises researchers from Birmingham, Bangor, Manchester, IGCAR and BARC, supporting early career researchers, and two-way research and academic visits.In order to meet the UK and India's future energy demand and decarbonisation commitments under the Paris Agreements nuclear energy will be of vital importance. Both the UK and India are developing future Generation IV nuclear fission technologies that would reduce the cost and waste production of nuclear energy, whilst being intrinsically 'walk away' safe. Gen IV reactor designs employ advanced coolants, such as molten metal (e.g. Na), molten salt, or gas coolants, which require high operation temperatures of 500-800 degrees C. This is significantly higher than current water cooled reactors, and as such requires advanced structural materials with increased capability over those currently employed.A variety of advanced materials are under consideration and development to meet the needs of Gen IV reactors and their more aggressive conditions (coolant chemistry, temperature and radiation damage) when compared to current reactors. Despite major successes there remains significant challenges to obtain the required balance of properties for Gen IV advanced reactors and a continued need to develop new materials.A material that has shown significant promise and has opened up a new research area is Oxide dispersion strengthened (ODS) steels, developed over the last 30 years. However, there remains challenges related to manufacturability on commercial scales. In the last decade there has been rapid development of advanced intermetallic reinforced steels for non-nuclear, with exceptional improvement in properties. This has been driven by great improvement in materials modelling, namely atomic scale modelling (DFT) and thermodynamic databases (CALPHAD), allowing for acceleration of the alloy development process. In this work we propose a new approach learning from the successes of nuclear ODS-steels, non-nuclear intermetallic reinforced steels, and the advances in materials modelling. A new generation of creep-resistant ODS-like 'Intermetallic Dispersion Strengthened' 'IDS-steels' will be developed capable of withstanding the demanding operating requirements of Generation IV reactors.Two-way knowledge exchange between the UK and India is a core part of this proposal such that long-lasting connections are developed that go beyond the duration of grant. This is highlighted throughout the Work Packages where expertise from both sides are combined. These strong interlinks will be ensured by bi-yearly visits of 1-2 weeks alternating between the UK and India including embedded researcher time in the resective labs, quarterly UK meetings including conference calls to India, with the findings of the project then presented at an open end-of-grant UK-India workshop.
期刊论文(1)
专著(0)
科研奖励(0)
会议论文
Influence of precipitate and grain sizes on the brittle-to-ductile transition in Fe-Al-V bcc-L21 ferritic superalloys
析出相和晶粒尺寸对 Fe-Al-V bcc-L21 铁素体高温合金脆塑转变的影响
DOI: 10.1016/j.msea.2022.144031
发表时间: 2022
期刊: A
影响因子: --
作者: [Ferreirós P]
通讯作者: Ferreirós P
Bcc-superalloys: Engineering Resilience to Extreme Environments
  • 批准号:
    MR/T019174/1
  • 项目类别:
    Fellowship
  • 资助金额:
    $155.73万
  • 财政年份:
    2020
  • 负责人:
    Alexander Knowles
  • 依托单位:
High Temperature Zirconium Alloys for Nuclear Fusion and Generation IV Fission Reactors
  • 批准号:
    EP/T01220X/1
  • 项目类别:
    Research Grant
  • 资助金额:
    $38.45万
  • 财政年份:
    2020
  • 负责人:
    Alexander Knowles
  • 依托单位:
海外基金