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

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

Comparative study of deuterium retention and vacancy content of self-ion irradiated tungsten 150 150 Mathew

Self-ion irradiation of pure tungsten with 2 MeV W ions provides a way of simulating microstructures generated by neutron irradiation in tungsten components of a fusion reactor. Electron microscopy has been used to characterize defects formed in tungsten samples by ion irradiation and estimate their density and size distribution. Some of the samples exposed to self-ion irradiation were then implanted with deuterium. Thermal Desorption Spectrometry (TDS) analysis was performed to estimate the deuterium inventory as a function of irradiation damage and deuterium release as a function of temperature. Application of Positron Annihilation Spectroscopy (PAS) to self-irradiated but not deuterium implanted samples enabled an assessment of the density of irradiation defects as a function of exposure to high-energy ions. The PAS results show that the density of defects saturates at doses in the interval from 0.085 to 0.425 displacements per atom (dpa). These results are discussed in the context of recent theoretical simulations exhibiting the saturation of defect microstructure in the high irradiation exposure limit.

Collection:
Journals
Journal:
Journal of Nuclear Materials
Publisher:
Elsevier
Published date:
15/11/2021