This paper reports on Polish involvement in experimental campaigns at European tokamaks. The achievements of the activities are related to plasma impurity study in ITER-oriented research program. It is conducted under two EUROfusion projects, WPJET1: JET Experimental Campaigns and WPMST1: Medium-Size Tokamak Campaigns. This contribution shows the recent progress of the integration methods in order to control and minimise metallic impurity content in different plasma conditions. The one of the objectives was a deeper understanding of physical processes governing Ion Cyclotron Resonance Heating (ICRF) heating and plasma wall interactions (PWI). Impurities studies are performed by means of X-ray and VUV spectroscopy diagnostics. Modelling for interpretation of the experimental analysis consist an integral part of the performed research. The transport codes are used to analyze possibility of radiation energy loses due to impurities which had been induced in the system in order to reduce heat loads of the divertor.