INNUMAT: Innovative Structural Materials for Fission and Fusion
INNUMAT: Innovative Structural Materials for Fission and Fusion
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 --
中文摘要
INNUMAT的目标是开发用于核应用的创新结构材料,并使它们走上符合裂变铅冷和熔盐快堆以及聚变演示的轨道。高熵合金(HEAs)是一种具有巨大发展潜力和非常有前途的新材料,以及氧化铝形成奥氏体(AFA)钢,已经被确定为第四代和小型模块化反应堆的潜在结构材料,也是先进材料解决方案的主要焦点,特别是用于铅冷却快堆的焊缝覆盖层和涂层15-15Ti,以及其他MYRRHA和ALFRED。和涂覆EUROFER和高级氧化物分散强化(ODS)钢用于熔合DEMO。其中一些结构材料在核领域之外也有潜在的适用性,例如在聚光太阳能和/或H2约束中。因此,该项目是跨领域的,因为目标应用以及它所追求的材料发现、筛选和鉴定的加速方法,应用于不同的技术准备水平(trl)。所考虑的材料在TRL、应用条件和要求上的差异导致了不同的目标,从而导致了项目中不同的研究轨迹,甚至不同的努力。共同的目标是迅速提高TRL,以满足所需的核应用对耐腐蚀性、高温强度、热稳定性和辐照耐受性的要求,这些都是目前结构材料无法满足的。因此,将应用计算和实验高通量材料筛选方法,并建立加速鉴定的路线图,为更高效、安全、可持续的核能系统铺平快速道路,为开发减少/零二氧化碳排放的经济能源系统的总体任务做出重大贡献。
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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