NSERC/UNENE Industrial Research Chair in Nuclear Materials

工业研究主席计划支持燃料通道的寿命管理，这是一个关键的机械 CANDU（R）核动力反应堆中的系统。它支持CANDU业主集团的研发计划， 解决现有27个运行反应堆的寿命管理问题，以及 坎杜能源公司和加拿大核实验室开发改进的燃料通道材料和设计， 在短期、中期和长期内，对现有工厂和未来的CANDU发电厂进行翻新。 其目的是促进对核材料的基本了解和发展应用技术 这是该行业在该领域的要求。这包括核材料辐射引起的变形 （特别是锆合金），这种材料的断裂性能和性能与 制造变量、晶体织构和微观结构。 有五大研究主题： 1.锆合金变形的实验研究（塑性、蠕变、疲劳） 2.辐照对Zr和Ni合金变形和显微组织的影响及对断裂的影响（B） （疲劳、氢化物性能、DHC） 3.稀土对锆合金性能的影响 4.模拟：a）Zr合金的变形，B）Zr合金的形变效应 5.α-β锆合金显微组织和织构的控制。 该计划还有助于培养研究生在一个领域有一个专家HQP的强烈需求。

The Industrial Research Chair program supports the life management of the fuel channel, a key mechanical system in a CANDU(R) nuclear power reactor. It supports the CANDU Owner's Group R&D program to address life management issues in the existing fleet of 27 operating reactors, as well as research programs at Candu Energy and Canadian Nuclear Laboratories to develop improved fuel channel materials and designs for refurbishment 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 technology required 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 to manufacturing 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 alloys 4.Modelling: a) of deformation, and b) of effect of hydrides on Zr alloys 5.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.