AbstractThe paper is a review of results of some fusion safety studies performed in Russia during 1996–2000 (after the 6th IAEA Technical Committee Meeting on ‘Developments in Fusion Safety’). In particular, changes of hydrogen isotope inventory in co-deposited layers on tungsten and graphite under simulation of normal tokamak operation and plasma disruptions are reported. Size distribution of graphite and W-Be-dust under the experiments at issue revealed two maximums. Erosion products were collected within tokamak T-10. Their microstructure and chemical composition were studied and are reported in the paper. Chemical interaction of beryllium powder with steam (in temperature range of 400–600°C) and air (at 500–1000°C) was investigated. Mathematical models describing it were developed. Chemical interaction of Be-powder with carbon was studied too. A dependence of beryllium carbide layer thickness growth versus time at 950°C was found on the basis of the experiments.