Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten

Self-ion irradiation of pure tungsten with 2 MeV W ions provides a way simulating microstructures generated by neutron in components fusion reactor. Transmission electron microscopy (TEM) has been used to characterize defects formed samples ion irradiation. It was found that irradiated 0.85 dpa at relatively low temperatures develops characteristic microstructure dominated dislocation loops and black dots. The density size distribution these were estimated. Some the exposed self-ion then implanted deuterium. Thermal Desorption Spectrometry (TDS) analysis performed estimate deuterium inventory as function damage release temperature. Increase increasing dose followed slight decrease above 0.1 found. Application Positron Annihilation Spectroscopy (PAS) self-irradiated but not enabled an assessment exposure high-energy ions. PAS results show saturates doses interval from 0.085 0.425 displacements per atom (dpa). These are discussed context recent theoretical simulations exhibiting saturation defect high limit. agrees simulation data described paper.