The Precipitation and redistribution of alloying element in Zircaloy-4 cladding tube oxidized in high-temperature steam

天谷 政樹

High Temperature Corrosion of Materials, 101(3), p.455 - 469, 2024/06

https://doi.org/10.1007/s11085-023-10216-9

Zirconium (Zr)-based alloys are widely used as fuel cladding material for light water reactors. Under a loss-of-coolant accident (LOCA) condition, the oxidation of fuel cladding by high-temperature steam induces the degradation of mechanical properties of the cladding and would affect the integrity of fuel rods and/or assemblies, etc., during LOCA. In this study, the distribution of the elements (zirconium, oxygen, tin, iron and chromium) in Zircaloy-4 cladding specimens oxidized in the temperature range of 1350- 1700 K in steam was analyzed along the radial direction of the specimens by using SEM/EPMA, and the cause of element distribution in the specimens was discussed in consideration of the morphology of precipitates in the specimens and hypothesized phase diagrams related to the elements contained in the specimens. The form of the particles precipitated and the comparison between SEM/EPMA results and hypothesized phase diagrams of Zr-Sn-O system suggested that the liquefaction of tin-rich material and/or Zr-(Fe,Cr) compounds occurred during the oxidation test. The results obtained indicate that Zircaloy-4 cladding tubes would start melting at the melting point of tin-oxide and the eutectic point of Zr-(Fe,Cr)compounds, which is much lower than the melting point of Zr, -Zr(O), or zirconium oxide (ZrO).