Radiation Damage and Effect of Temperature, from Gen 3 to SMR Relevant Temperatures

辐射损伤和温度影响（从 Gen 3 到 SMR 相关温度）

• 批准号: 580443-2022
• 负责人: Daymond, MarkMR
• 金额: $ 8.74万
• 依托单位: Queen's University
• 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=759801
• 关键词: Radiation; Damage; Effect; Temperature; Gen

The proposed research will combine experimental and modelling approaches to determine the effect of neutron radiation on three common Fe- and Ni-based alloys at the elevated temperatures that small modular reactors (SMRs) operate at. Proton irradiation will be used to emulate the effects of neutron irradiation, and hence to develop approaches allowing accelerated material qualification and assessment for use in novel reactor designs. Transmission Electron Microscopy (TEM) and X-ray diffraction will be used to characterise radiation damage structures and elemental segregation, while modelling will be used to simulate both aspects, and help provide mechanistic insight into the variation with temperature. This collaborative research will train three PhD students, and include complementary experimental and computational aspects that will help inform regulatory qualification of structural materials for SMRs. The key technology knowledge gap limiting progress and rapid deployment of SMRs is materials performance under SMR-relevant conditions. Most past nuclear materials' research has focused on behaviour at traditional reactor operating temperatures, which means that new scientific insights are necessary for proper SMR materials selection and qualification. Addressing these knowledge gaps by studying what nanoscale mechanisms are at play at these elevated temperatures will be critical for the CNSC to be able to make scientifically informed decisions. This will help new reactor designs be implemented, reducing electricity and power costs for Canadians.

拟议的研究将结合实验和建模方法，以确定在小型模块化反应堆（smr）运行的高温下中子辐射对三种常见的铁基和镍基合金的影响。质子辐照将被用来模拟中子辐照的效果，从而开发出一种方法，允许在新型反应堆设计中使用的加速材料鉴定和评估。透射电子显微镜（TEM）和x射线衍射将用于表征辐射损伤结构和元素偏析，而建模将用于模拟这两个方面，并帮助提供随温度变化的机理见解。这项合作研究将培养三名博士生，并包括互补的实验和计算方面，这将有助于为smr结构材料的监管资格提供信息。限制smr进展和快速部署的关键技术知识差距是smr相关条件下的材料性能。过去大多数核材料的研究集中在传统反应堆工作温度下的行为，这意味着新的科学见解对于适当的SMR材料选择和鉴定是必要的。通过研究纳米尺度机制在这些高温下的作用来解决这些知识缺口，对于CNSC能够做出科学决策至关重要。这将有助于实施新的反应堆设计，降低加拿大人的电力和电力成本。