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 isoto
pe inventory in co-deposited layers on tungsten and graphite under simulati
on of normal tokamak operation and plasma disruptions are reported. Size di
stribution of graphite and W-Be-dust under the experiments at issue reveale
d two maximums. Erosion products were collected within tokamak T-IO. Their
microstructure and chemical composition were studied and are reported in th
e paper. Chemical interaction of beryllium powder with steam (in temperatur
e range of 400-600 degreesC) and air (at 500-1000 degreesC) was investigate
d. Mathematical models describing it were developed. Chemical interaction o
f 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 o
f the experiments. (C) 2001 Elsevier Science B.V. All rights reserved.