NSERC/UNENE/Nu-tech Precision Metals Industrial Research Chair in Nuclear Materials

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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