[en] Arc erosion measurements of the materials for limiters and first walls in fusion devices are of importance in the fusion technology so as to help in estimation of plasma contamination. In this brief report, erosion rates due to arcing were measured for 316 stainless steel, titanium, titanium nitride coated on graphite, and titanium carbides coated on 440C stainless steel and graphite. The characteristic features of the experiment for a simulation study of arc erosion in fusion devices were on the points that test materials were irradiated before arcing with deuterium ions, helium ions and heavy (''self'')-ions, and that the irradiated materials were arced in hydrogen plasma produced beforehand. The erosion was observed by a SEM and a surface roughness gage. The mass loss of materials was measured by a microbalance. As the effects of pre-irradiation, the results show that arcs were inductive at the irradiated region, and that the erosion rates were enhanced by irradiation