Fuel cladding materials research
Zirconium is a metal which is vital to the nuclear industry, but not widely studied within UK academia. The MPC is taking the lead to establish a focus for zirconium alloy research. Research also addresses the management of irradiated stainless steel fuel cladding and braces.
Characterisation and Modelling Precipitation and Matrix Chemistry of Zirconium Alloys
Maria Ivermark, PhD Student
To date, we lack any understanding of how the chemistry of the matrix might influence the corrosion properties of Zirconium alloys. The general aim of this project is to exploit new experimental methods to fully characterise the matrix chemistry together with precipitation distribution in Zirconium alloys. The experimental data will be used to develop a model predicting both microstructural aspects in such alloys. Further details on Characterisation and Modelling Precipitation and Matrix Chemistry of Zirconium Alloys.
Thermomechanical Processing of Zirconium-alloys
Victoria Allen, PhD Student
Zr-alloys, similar to MG and Ti alloys are prone to significant texture development during processing due to the limited number of slip planes available in the hexagonal structure. This has an affect on the rolling and pilgering process and the final properties of Zr-alloys such as ZIRLO. Further details Thermomechanical Processing of Zirconium-alloys.