Fig. 1: Oxidation behaviours of Zircaloy.
From: Oxidation of zirconium alloys for nuclear fuel cladding
(a) Development history of Zircaloys for nuclear fuel cladding; (b) Oxidation mechanism of Zircaloys; (c) Schematic diagram of the oxidation kinetics of Zircaloys. Reproduced with permission from ref. 15, copyright (ASTM International, 2008); (d) Scanning electron microscope image of oxides formed on Zircaloys at 1000 °C with 100 hPa of steam partial pressure for 10000 s. Reproduced with permission from ref. 16, copyright (Elsevier, 2021); (e) Weight gains versus time during oxidation at 900 °C for 2 h of a M5 alloy exposed to air Reproduced with permission from ref. 23, copyright (Elsevier, 2022); (f) Cross-sectional morphologies of M5 alloy oxidized in air at 900 °C for 80 min. Reproduced with permission from ref. 23, copyright (Elsevier, 2022).
