Investigation of oxidation resistance of carbon based first-wall liner materials of fusion reactors

Abstract One important aspect in selection of carbon based first-wall liner materials in fusion reactors is a sufficient oxidation resistance against steam and oxygen; this is because during accidents like loss of coolant into vacuum or loss of vacuum these oxidizing media can enter the vacuum vessel and may cause some corrosion of carbon followed by release of adsorbed tritium; in addition other consequences of oxidation like formation of burnable gases and their explosions have to be examined. Based on extensive experience on nuclear graphite oxidation in HTRs KFA has started in cooperation with NET some experimental investigations on oxidation of fusion reactor carbons. Results of first experiments on CFCs, Ti- and Si-doped carbons and graphites in steam (1273–1423 K) and oxygen (973 K) are reported. It was found that most materials have a similar reactivity as HTR nuclear graphites (which is much smaller than those of usual technical carbons); Si-doped CFCs however have a remarkably better oxidation resistance than those, which is probably due to the formation of a protecting layer of SiO 2 . The measured kinetic data will be used in safety analyses for above mentioned accidents.