Zr is used extensively in nuclear reactors worldwide in a broad range of microstructural conditions due to its thermomechanical, corrosion and neutronic properties. However the affinity between H and Zr leaves Zr-alloys susceptible to ZrH precipitation and delayed hydride cracking (DHC); a process controlled by the diffusion of H. The purpose of this work is to characterize the effect of the beta-Zr phase, cold work, grain morphology and anisotropy of the Zr hcp lattice on H mobility; building on the platform established by J.R. Santisteban et. al., whom have used neutronic techniques for the non-destructive determination of low H content in metals. On successful completion of this work in-situ experiments will be carried out on hydrogenated samples subjected to stress and the H diffusion to a stress concentration monitored providing fundamental insight into the DHC process.