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

• Published in: Journal of nuclear materials Vol. 509; pp. 145 - 151
• Main Authors: Tan, Y., Lian, Y.Y., Feng, F., Chen, Z., Wang, J.B., Liu, X., Guo, W.G., Cheng, L., Lu, G.H.
• Format: Journal Article
• Language: English
• Published: Elsevier B.V 01-10-2018
• Subjects: D retention; Deuterium ions; High energy rate forging; Morphology; W-Y2O3 alloy; High energy rate forging; W-Y2O3 alloy; D retention; Morphology; Deuterium ions
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2018.06.022

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.