Steam chemical reactivity experiments were conducted for several ITER-like tokamak plasma-facing-component (PFC) materials: NB31 and NS31 carbon fiber composites (CFCs), W-1%2a, DShG-200 Be, and Be.(S65C and-Ka-wecki PO Ductile Be) specimens irradiated to fast neutron fluences ranging from 5 x 10(19) to 1 x 10(21) n/cm(2). Experiments were performed at 800-1100 degreesC for CFC, 550-1000 degreesC for W-1%2a, 500-900 degreesC for unirradiated Be, and 600-800 degreesC for irradiated Be. Average hydrogen generation rates are presented for these new measurements as a function,of temperature, and the results are compared to previous studies on similar materials. In general, the new results extend the temperature and material range from previous studies, are consistent with previous work, and provide Arrhenius-type hydrogen generation expressions useful for safety assessment calculations. Little irradiation influence on oxidation behavior was observed for Be irradiated to 1 x 10(21) n/cm(2), whereas significant influence was observed in previous tests on Be irradiated to 5 x 10(22) n/cm(2). (C) 2002 Elsevier Science B.V. All rights reserved.
Times Cited: 4 B 10th International Conference on Fusion Reactor Materials (ICFRM-10) Oct 14-19, 2001 Baden-basen, germany Forschungszentrum Karlsruhe; EURATOM Fus Assoc 4