The 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-IO. 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 degreesC) and air (at 500-1000 degreesC) 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 degreesC was found on the basis of the experiments. (C) 2001 Elsevier Science B.V. All rights reserved.