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Surface erosion effects of candidate fusion materials

Conference · · Fusion Technol.; (United States)
OSTI ID:5652089
Some candidate fusion materials such as nickelbase alloys and graphites were studied, because of their importance as first wall components in CTR devices. Polycrystalline samples of Inconel 600, Inconel 625, Nimonic alloy PE 16, nuclear grade graphite ATJ and pyrolytic graphite were investigated. Results for surface damage and topography, blistering, flaking, ion erosion and sputtering yields are reported for irradiations with low energy He/sup +/ ions (5-12 keV) at room temperature, using total ion doses up to 2 x 10/sup 19/ ions cm/sup -2/. SEM, TEM and AES analyses were used to identify surface damage, structure and compositional changes after irradiation. Comparative studies of the ion erosion yield of nickel-base alloys, as measured by the step-height technique, were made. Total sputtering yields were determined dynamically for sputtered films of these alloys using a quartz crystal microbalance. The yields were studied as a function of ion dose, energy and surface roughness.
Research Organization:
J. Stefan Institute, ''E. Kardelj'' University, Ljubljana
OSTI ID:
5652089
Report Number(s):
CONF-8309103-
Conference Information:
Journal Name: Fusion Technol.; (United States) Journal Volume: 6:2
Country of Publication:
United States
Language:
English