Improving the high-temperature oxidation resistance of commercial Zr-alloys

School of Materials

University of Manchester

In modern nuclear reactors fuel cladding is based on zirconium alloys due to their good performance in the environment of water-cooled reactors and their transparency to neutrons. The time the cladding material can operate in such an environment (and therefore the level of energy that can be produced from a fuel assembly) is proportional to the corrosion properties. To date, any development in improving the corrosion performance of such alloys has been purely empirical and has not resulted in the required step change, which would significantly increase the efficiency of uranium utilisation in nuclear power plants.

In order to understand the mechanisms of zirconium corrosion under these conditions a study of Zr oxidation and hydriding (i.e. the anodic and cathodic processes) is critical. The project will thus involve a detailed investigation of the corrosion and electrochemistry of Zr and its alloys in aqueous environments at elevated temperature and pressure. A key component of the study shall be to measure, using electrochemical methods, the ionic and electronic transport properties of the oxide as a function of alloy composition and environment. Understanding of these factors, and how they change with time, is critical in developing a full mechanism of the oxidation process in zirconium.

The research will be undertaken by a multi-university team, encouraging PhD students and post-doctoral research associates to form a core group of researchers who work together to exploit world-class facilities from different institutions.