Testing of Advanced Nanoparticle Dispersed Steels for Next Generation Reactors

我的研究生涯主要集中在研究反应堆材料的辐射效应和未来核材料的发展。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坚韧挑战。因此，两年前，我们开始了一个ODS计划，得到了我之前在女王大学获得的NSERC发现资助的支持。在我们的建议中，马氏体和奥氏体ODS钢都将被研究。马氏体ODS钢主要基于Fe-9%Cr合金，奥氏体ODS钢基于316和310不锈钢。我们的计划目标是在未来五年内对这些材料进行冶金加工进步和综合性能测试。我和我的学生将专注于我们以前设计的ODS钢的完整微观结构表征和辐照测试。全面的研究将提供对（1）过程诱导的微观结构的良好理解，例如晶粒形态，颗粒尺寸和空间分布以及元素的化学图，这将为我们在中国的合作者的制造团队提供准确的反馈，以便进一步开发，以及（2）离子辐照下的辐照行为，以模拟反应堆中发现的中子辐照条件，在（3）原子位移和缺陷聚集的分子动力学模拟和（4）确定辐照性质与所设计的微结构之间的相关性的支持下。以上概述的研究问题将突出辐照诱导的力学行为的微观结构响应的重要性。从这项研究中了解到的信息将扩大我们对ODS钢在某些条件下如何表现的了解，使我们了解其结构特性，并导致能够承受核环境严酷条件的配方。 研究结果将为选择抗辐射损伤的材料提供依据，并指导未来材料的设计。此外，由于消耗臭氧层物质钢具有特殊的高温蠕变 * 和耐腐蚀性以及耐辐照性，它们还具有很大的潜力 *，可用作聚光太阳能发电厂、* 喷气发动机、化学反应堆的结构材料，以及利用水的热能生产氢。因此，这项研究将导致核技术和材料研究的进步，造福于安大略和所有加拿大人。本研究建议中的信息和设施共享将支持和加强当前的国际合作。此外，由于这项建议，我们将为下一代研究人员提供高水平的HQP培训。

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.