We would like to congratulate Patrick Burr in completing his PhD on Ab-initio modelling of Zr and Be alloys for nuclear applications. His work on zirconium alloys has identified a novel mechanism responsible for the microstructural evolution of nuclear fuel cladding due to irradiation. This knowledge may provide the basis for the development of improved Zr fuel cladding with higher radiation tolerance and corrosion resistance. At the same time, his work on beryllium alloys (used in satellite components and fusion reactors) showed that the mechanical and chemical properties of the metal may be improved by carefully alloying with small additions of Fe.

Read more about his thesis here page.