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CANDU（R）核电反应堆中的一个关键机械系统。它支持CANDU业主集团的研发计划，以 ** 解决现有27个运行反应堆的寿命管理问题，以及 **Candu Energy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和设计，用于 ** 现有工厂的翻新和未来的CANDU电厂的短期，中期和长期。其目的是促进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）的辐射诱发变形、这类材料的断裂特性以及这些特性与 ** 制造变量、晶体结构和微观结构的关系。主要研究内容有以下五个方面：1.锆合金变形的实验研究（塑性、蠕变、疲劳）** 2.辐照的影响：a）对Zr和Ni合金的变形和显微组织，和B）对断裂的影响 **（疲劳、氢化物性质、DHC）** 3.氢化物对Zr合金性质的影响 ** 4.建模：a）变形，和B）退火对Zr合金的影响 ** 5. α-β锆合金的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.