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Oxidation Behavior of Zirconium Hydride in Zirconium Alloys in Superheated Steam at 400?C
锆合金中的氢化锆在400℃过热蒸汽中的氧化行为
2017
Nuclear Science and Technology
锆合金中的氢化锆在400℃过热蒸汽中的氧化行为
To investigate the oxidation of zirconium hydride, the corrosion test on pre-hydrided SZA-4 alloy prepared by gaseous hydrogen charging method was performed in an autoclave. Results showed that under high tensile stress produced in α-Zr matrix at the oxide/metal (O/M) interface, hydride reorientation took place and led to the transition from δ-ZrH1.66 (fcc structure) parallel to the O/M interface to ε-ZrH2 (fct structure) perpendicular to the O/M interface. ε-ZrH2 oxidized faster than α-Zr matrix, and was oxidized to m-ZrO2(monoclinic ZrO2).
doi:10.12677/nst.2017.52011
fatcat:7k5r5rycpvam3lpcorzpyy2k2a