NSERC/UNENE Industrial Research Chair in Nuclear Materials

工业研究主席项目支持燃料通道的寿命管理，这是CANDU(R)核反应堆的关键机械系统。它支持CANDU所有者集团研发项目，以解决现有27个运行反应堆的寿命管理问题，以及CANDU能源和加拿大核实验室的研究项目，以开发改进的燃料通道材料和设计，用于现有工厂和未来CANDU发电厂的短期、中期和长期翻新。其目的是进一步了解核材料的基本知识，并开发该领域工业所需的应用技术。这包括核材料（特别是锆合金）的辐射引起的变形，这些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的关系。主要有五个研究主题：1。Zr合金变形（塑性、蠕变、疲劳）的实验研究辐照对Zr和Ni合金变形和显微组织的影响；辐照对断裂（疲劳、氢化物性能、DHC）的影响氢化物对Zr合金性能的影响建模：a)变形，b)氢化物对Zr合金的影响5。α - β锆合金组织与织构的控制。该项目还用于培养对HQP专家有强烈需求的领域的研究生。

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.