Surface modification and deuterium retention of high energy rate forging W-Y2O3exposed to deuterium plasma

W-Y2O3 alloy was processed by high energy rate forging at 1823 K. Irradiation resistance of the well-developed W-Y2O3 alloy against 50 eV deuterium (D) ions with total fluences ranging from 2.2 × 1025 D·m−2 to 1.3 × 1026 D·m−2 was performed in a linear plasma device. During irradiation, the ion flux was up to 1.2 × 1022 D·m−2·s−1 and the temperatures of the samples were kept at 443-463 K. Both the surfaces of perpendicular to (Plane-A) and parallel to (Plane-B) the forging axis were irradiated. After irradiation, D retentions of the irradiated samples were measured by thermal desorption spectroscopy (TDS). The experimental results show that a large number of small-blisters (≤3 μm) were formed on the irradiated Plane-A while hardly formed on the other. However, D retention of the irradiated Plane-B is larger than that of the irradiated Plane-A. The underlying mechanisms are discussed.