Surface analytical investigation of the tritium getter ZrCO after exposure to various gases

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ZrCo is a hydride forming material frequently investigated and proposed for storage and handling of hydrogen isotopes. It is of special interest for deuterium and tritium storage needed for the operation of a nuclear fusion reactor. An interaction of ZrCo powder with contaminant gases particularly during the thermal release of the hydrogen isotopes from the hydride at temperatures above 300 °C was found to cause a reduction of the reactivity of the powder. Consequently, a serious decrease of the hydrogen storage capacity occurs. From surface analytical investigations of ZrCo after exposure to the contaminant gases CO, CO2, O2, N2, CH4, and C2H4 it was concluded that CH4, C2H4, O2, or N2 react predominantly with Zr, the principal hydride forming alloy component, to carbide, nitride, and/or oxide. The resulting decrease of the storage capacity is possibly due to either a reduction in the amount of unreacted Zr available for the formation of Zr hydrides or to a formation of a thick protective overlayer. CO or CO2, which react mainly with the Co component but with Zr in surface near layers only, cause a less pronounced decrease in storage capacity.