Combined effects of temperature and of high hydrogen and oxygen contents on the mechanical behavior of a zirconium alloy upon cooling from the βZr phase temperature range

During hypothetical loss-of-coolant accidents (LOCA), zirconium-based nuclear fuel claddings can be exposed to high temperatures in the βZr phase domain and absorb substantial amounts of hydrogen (up about 3000 weight ppm) oxygen 1 %). This paper provides novel data combined effects contents on mechanical behavior (prior-)βZr phase, as a function temperature, upon cooling from temperature range. A protocol was developed homogeneously charge Zircaloy-4 cladding tubes at different contents, up 3200 ppm, between 0.13 0.9 wt%. Tensile tests were then performed various 700 °C 30 domain. The results show that strongly depends testing contents. Relationships are proposed describe macroscopic ductile-to-brittle transition material predictions based these relationships compared selected literature obtained oxidized including semi-integral LOCA tests. Also, it is shown considering necessary interpret material's behavior, particularly embrittlement subjected LOCA-relevant secondary hydriding.