Testing of Advanced Nanoparticle Dispersed Steels for Next Generation Reactors

用于下一代反应堆的先进纳米粒子分散钢的测试

• 批准号: RGPIN-2016-04455
• 负责人: yao, zhongwen
• 金额: $ 2.4万
• 依托单位: Queen's University
• 依托单位国家: 加拿大
• 项目类别: Discovery Grants Program - Individual
• 财政年份: 2020
• 资助国家: 加拿大
• 起止时间: 2020-01-01 至 2021-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=709318
• 关键词: Testing; Advanced; Nanoparticle; Dispersed; Steels

My research career is focused on the investigation of radiation effects of reactor materials and development of future nuclear materials. Oxide dispersion strengthened steels (ODS) are probably the most promising structural materials that could handle the tough challenges involved in the design of the next generation of nuclear reactors. Therefore we started an ODS program two years ago with support from my previous NSERC Discovery Grant at Queen's. In our proposal both martensitic and austenitic ODS steels will be investigated. Martensitic ODS steels are mainly based on Fe-9% Cr alloys, and austenitic ODS steels are based on 316 and 310 stainless steels. Our program targets the metallurgical processing advancement and comprehensive property testing of these materials over the next five years. I and my students will focus on the complete microstructure characterization and irradiation testing of the ODS steels we previously designed. The comprehensive investigation will provide a good understanding of (1) process induced microstructures, such as grain morphology, particle size and spatial distribution and chemical map of elements, which will give accurate feedback to the manufacturing group of our collaborators in China for further development, and (2) irradiation behaviour under ion irradiation, to simulate the neutron irradiation conditions found in reactors, with support of (3) molecular dynamics simulation of atomic displacement and defect clustering and (4) determine the correlation between irradiation properties and the designed microstructures. The above outlined research issues will highlight the importance of microstructure response on irradiation induced mechanical behaviours. The information learned from this research will expand our knowledge about how ODS steels perform under certain conditions, give us an understanding of their structural properties, and lead to formulations that could withstand the rigors of a nuclear environment. Results will provide useful ground for selection of materials that are more resist radiation damages which will guide the design of future materials. In addition, since ODS steels possess exceptional high-temperature creep and corrosion and irradiation resistance they also have great potential for use as structural materials for concentrated solar power plants, jet engines, chemical reactors as well as for hydrogen production from thermolysis of water. As a result, this research will lead to advancements in nuclear technologies and materials research, to the benefit of Ontario and all Canadians. The sharing of information and facilities featured in this research proposal will support and enhance current international collaborations. In addition, thanks to this proposal, we will provide a high level of HQP training to the next generation of researchers.

我的研究生涯主要集中在反应堆材料辐射效应的研究和未来核材料的开发。氧化物弥散强化钢（ODS）可能是最有前途的结构材料，可以应对下一代核反应堆设计中的严峻挑战。因此，在我之前在女王大学获得的 NSERC 发现资助金的支持下，我们于两年前启动了 ODS 项目。在我们的提案中，将对马氏体和奥氏体 ODS 钢进行研究。马氏体ODS钢主要以Fe-9%Cr合金为基础，奥氏体ODS钢以316和310不锈钢为基础。我们的计划目标是在未来五年内实现这些材料的冶金加工进步和综合性能测试。我和我的学生将重点关注我们之前设计的 ODS 钢的完整微观结构表征和辐照测试。全面的研究将有助于更好地理解（1）过程诱导的微观结构，如晶粒形态、颗粒尺寸和空间分布以及元素的化学图谱，这将为我们中国合作者的制造小组提供准确的反馈，以供进一步开发；（2）离子辐照下的辐照行为，以模拟反应堆中的中子辐照条件，并在（3）原子位移和原子位移的分子动力学模拟的支持下进行。 缺陷聚类和（4）确定辐照特性和设计的微观结构之间的相关性。上述研究问题将凸显微观结构响应对辐照诱导机械行为的重要性。从这项研究中获得的信息将扩大我们对消耗臭氧层物质钢在特定条件下如何表现的了解，让我们了解其结构特性，并开发出能够承受核环境严酷的配方。 研究结果将为选择更能抵抗辐射损伤的材料提供有用的基础，从而指导未来材料的设计。此外，由于 ODS 钢具有出色的高温蠕变性能 且耐腐蚀、耐辐照也有很大的潜力 用作聚光太阳能发电厂的结构材料， 喷气发动机、化学反应器以及氢气生产 水的热分解。因此，这项研究将推动核技术和材料研究的进步，造福安大略省和所有加拿大人。本研究提案中的信息和设施共享将支持和加强当前的国际合作。此外，由于这项提案，我们将为下一代研究人员提供高水平的 HQP 培训。