Multi-scale modelling of Refractory High-Entropy Alloys materials for Small Modular Reactors

小型模块化反应堆耐火高熵合金材料的多尺度建模

• 批准号: 580475-2022
• 负责人: TetsassiFeugmo, ConrardGiresseTFGC
• 金额: $ 8.74万
• 依托单位: University of Waterloo
• 依托单位国家: 加拿大
• 项目类别: Alliance Grants
• 财政年份: 2022
• 资助国家: 加拿大
• 起止时间: 2022-01-01 至 2023-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=747689
• 关键词: Multi; scale; modelling; Refractory; Entropy

SMRs are typically anticipated to have an electrical power output of less than 300 MWe (electric) or less than 1000 MWth (thermal). They offer many advantages, such as relatively small physical footprints, reduced capital investment, the ability to be sited in locations not possible for larger nuclear plants, and provisions for incremental power additions. During operation, the reactor pressure vessel material is exposed to high temperatures exceeding 1000°C, radiation, and corrosion, resulting in localized embrittlement of the vessel and welds in the reactor core. As the reactor vessel is considered irreplaceable, these demanding operating environments require the development of new alloy materials that can withstand their increased physical, chemical, thermal, and radiation-related challenges, as well as computational approaches to predict their behavior under operation conditions. High Entropy Alloys (HEAs) are a promising option, due to their composition which can be tuned over a wide range of possibilities to optimize high-temperature mechanical properties, radiation, and corrosion resistance, and obtain improved performances compared to conventional materials. However, current knowledge of HEAs properties is still less advanced compared with conventional alloys, and further studies are needed to assess the opportunities they offer. Refractory HEAs (RHEAs) are of particular interest to the nuclear community due to their retention of mechanical properties at high temperatures, reduced defect production, and resistance to irradiation-induced swelling and hardening. However, the mechanism behind these observations is still not well understood because of the lack of computational. In this regard, the proposed research activity will develop a Phase Field Crystal (PFC) model for HEAs to understand their properties as well as environmental degradation mechanisms. In addition to the design of new materials for the body of the SMRS vessel, our result will provide valuable information that can improve the reliability of systems, structures, and components during normal, abnormal, and long-term operations.

通常预计SMR的电力输出少于300 MWE（电动）或小于1000 MWTH（热）。它们提供了许多优势，例如相对较小的物理足迹，减少资本投资，可以放置在较大核电站不可能的位置的能力以及增加功率的规定。在操作过程中，反应堆压力容器材料暴露于超过1000°C，辐射和腐蚀的高温，从而导致局部对血管和反应堆芯中的温暖。由于反应堆容器被认为是不可替代的，因此这些苛刻的操作环境需要开发新的合金材料，这些材料可以承受其物理，化学，热和辐射相关的挑战，以及在操作条件下预测其行为的计算方法。高熵合金（HEAS）是一个承诺的选择，因为它们的组成可以在广泛的可能性中进行调整，以优化高温机械性能，辐射和耐腐蚀性，并与常规材料相比获得改进的性能。但是，与传统合金相比，当前对HEAS性质的知识仍然不那么先进，并且需要进一步的研究来评估它们提供的机会。难治性HEAS（RHEAS）由于在高温下保留了机械性能，减少缺陷产生以及对辐射引起的肿胀和硬化的耐药性，因此特别感兴趣。但是，由于缺乏计算，这些观察结果背后的机制仍未得到充分理解。在这方面，拟议的研究活动将开发出一个相位晶体晶体（PFC）模型，以了解其特性以及环境降解机制。除了设计新材料的SMRS船只外，我们的结果还将提供有价值的信息，可以在正常，异常和长期操作期间提高系统，结构和组件的可靠性。