NSERC/UNENE Industrial Research Chair in Nuclear Materials

工业研究教席计划支持燃料通道的寿命管理，燃料通道是CANDU(R)核动力反应堆中的关键机械系统。它支持CANDU所有者的集团研发计划，以解决现有27个运行中的反应堆机队的寿命管理问题，以及坎杜能源和加拿大核实验室的研究计划，以开发改进的燃料通道材料，并为两个现有工厂和未来的CANDU发电厂的短期、中期和长期翻新设计。目的是加深对核材料的基本了解，并开发该行业在这一领域所需的应用技术。这包括核材料(特别是锆合金)的辐照变形、这类材料的断裂性能以及性能与制造变量、晶体织构和微观结构之间的关系。主要研究内容有五个：1.锆合金变形(塑性、蠕变、疲劳)的实验研究2.辐照对锆和镍合金变形和组织的影响；b)对断裂的影响(疲劳、氢化物性能、DHC)3.氢化物对锆合金性能的影响4)变形模型：a)变形和b)氢化物对锆合金的影响5.α-β锆合金的组织和织构的控制。该计划还用于在对专家HQP有强烈需求的领域培养研究生。

The Industrial Research Chair program supports the life management of the fuel channel, a key mechanicalsystem in a CANDU(R) nuclear power reactor. It supports the CANDU Owner's Group R&D program toaddress life management issues in the existing fleet of 27 operating reactors, as well as research programs atCandu Energy and Canadian Nuclear Laboratories to develop improved fuel channel materials and designs forrefurbishment of both existing plants and for future CANDU power plants in the short, medium and long term.The purpose is to further the fundamental understanding of nuclear materials and to develop applied technologyrequired by the industry in this area. This includes radiation-induced deformation of nuclear materials(especially zirconium alloys), the fracture properties of such materials and the relationship of properties tomanufacturing variables, crystallographic texture and microstructure.There are five major research themes:1.Experimental studies of the deformation of Zr alloys (plasticity, creep, fatigue)2.Effect of irradiation: a) on the deformation and microstructure of Zr and Ni alloys, and b) on fracture(fatigue, hydride properties, DHC)3.Effects of hydrides on the properties of Zr alloys4.Modelling: a) of deformation, and b) of effect of hydrides on Zr alloys5.Control of microstructure and texture of alpha-beta zirconium alloys.The program also serves to train graduate students in an area where there is a strong demand for expert HQP.