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INNUMAT: Innovative Structural Materials for Fission and Fusion

INNUMAT: Innovative Structural Materials for Fission and Fusion
INNUMAT:用于裂变和聚变的创新结构材料
批准号:
10047145
负责人:
金额:
$20.3万
依托单位:
依托单位国家:
英国
项目类别:
EU-Funded
财政年份:
2022
资助国家:
英国
项目状态:
未结题
起止时间:
2022 至 --

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中文摘要
翻译
INNUMAT的目标是开发用于核应用的创新结构材料,并使它们走上裂变、铅冷却和熔盐快堆以及聚变演示的资格轨道。高熵合金(HEAS)是一种具有巨大发展潜力和非常有前途的性能的新型材料,以及氧化铝形成奥氏体(AFA)钢,已被确定为第四代反应堆和小型模块化反应堆的潜在结构材料,也是主要关注的焦点,其中也考虑了先进材料解决方案,特别是用于铅冷却快堆的堆焊层和涂层15-15Ti,以及用于聚变演示的涂层EUROFER和先进的氧化物弥散强化(ODS)钢。其中一些结构材料在核领域之外也具有潜在的适用性,例如在聚光太阳能和/或氢气限制中。因此,该项目具有交叉性,是因为目标应用以及它追求的材料发现、筛选和鉴定的加速方法,这些方法适用于不同的技术准备程度。所考虑的材料在TRL、应用条件和要求方面的不同导致了不同的目标,因此在整个项目中的研究轨迹也不同,甚至努力程度也不同。共同的目标是迅速提高所需的核应用的TRL,以达到现有结构材料无法满足的耐腐蚀性、高温强度、热稳定性和抗辐射能力的要求。因此,将采用计算和实验的高通量材料筛选方法,并将制定加速鉴定路线图,为更有效、更安全、可持续的核能系统铺平一条快速道路,为发展减少/零二氧化碳排放的经济能源系统的总体使命作出重大贡献。
英文摘要
INNUMAT aims to develop innovative structural materials for nuclear applications and put them on track towards qualification for fission lead-cooled and molten salt fast reactors as well as fusion DEMO. High entropy alloys (HEAs), a new class of materials with a vast development potential and very promising properties, as well as alumina forming austenitic (AFA) steels, already identified as prospective structural materials for Gen IV and Small Modular Reactors, are in the main focus in which advanced material solutions are considered as well, in particular weld overlay and coated 15-15Ti for lead-cooled fast reactors, among others MYRRHA and ALFRED, and coated EUROFER and advanced oxide dispersion strengthened (ODS) steel for fusion DEMO. Some of these structural materials are of potential applicability also outside the nuclear field, e.g. in concentrated solar power and/or in H2 confinement. The project is thus cross-cutting because of the target applications as well as because of the accelerated methodologies for materials discovery, screening and qualification that it pursues, applied at different technology readiness levels (TRLs). The differences in TRL, application conditions and requirements of the considered materials result in different objectives and hence different research tracks through the project with even different efforts. Common goal is to rapidly increase the TRL for the desired nuclear applications towards requirements of corrosion resistance, high temperature strength, thermal stability and irradiation tolerance, which are not met by current structural materials. Therefore, computational and experimental high throughput material screening methods will be applied and roadmaps for accelerated qualification will be established paving a fast way to more efficient safe sustainable nuclear energy systems with considerable contribution to the overall mission of developing economic energy systems with reduced/zero CO2 emissions.
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