Oxidation and hydriding of Zr1%Nb alloys by steam at 900-1200 deg C

摘要

High temperature steam oxidation and the absorption of the hydrogen by Zr1%Nb cladding of WWER type nuclear reactor fuels were examined in the temperature range of 900-1200 deg C. The rate of mass gain and the formation of zirconium oxide and of alpha-Zr(O) layers was determined on the original WWER cladding tube samples, using metallographical testing. Hydrogen uptake of the samples was also measured. The results agree fairly well with literature data. (author). 25 refs., 19 figs., 3 tabs. (Atomindex citation 28:026030)