NSERC/UNENE/Nu-tech Precision Metals 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台运行中的RACKER机队的寿命管理问题，并支持加拿大原子能有限公司的研究计划，以开发改进的燃料通道材料和设计，以便在短期、中期和长期翻新现有工厂和未来一代CANDU发电厂。 其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)的辐射变形、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的关系。 主要研究主题有五个： 1.合金变形(塑性、蠕变、疲劳)的实验研究 2.辐射的影响： A)关于Zr和Ni合金的变形和显微组织 B)关于断裂(疲劳、氢化物性能、DHC) 3.氢化物对锆合金性能的影响 4.建模： A)变形 B)氢化物对锆合金的影响 5.α-β-锆合金的组织和织构控制

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 ractors, as well as research programs at Atomic Energy of Canada Ltd. to develop improved fuel channel materials and designs for refurbishment of both existing plants and for future generation of 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 b) on fracture (fatigue, hydride properties, DHC) 3.Effects of hydrides on the properties of Zr alloys 4.Modelling: a) of deformation b) of effect of hydrides on Zr alloys 5.Control of microstructure and texture of alpha-beta zirconium alloys