The effect of fast-neutron damage on the room-temperature tensile properties of zircaloy-2 and zircaloy-4 irradiated at low temperature ( < 100 °C) up to a fluence of 1.43 × 10 20 n/cm 2 ( > 1 MeV) and at elevated temperature (320–360 °C) up to 1.53 × 10 21 n/cm 2 (> 1 MeV) was investigated. The irradiation conditions at elevated temperature simulated those of fuel elements. The behaviour of irradiation-hardening of zircaloy-2 was similar to that of zircaloy-4. Considerable irradiation-hardening and loss of ductil'ty were observed. The rate of hardening for low-temperature irradiation was higher than that for elevated-temperature irradiation. Irradiation-induced changes in yield stress, Δσ y , showed saturation at a fluence of 4 × 10 19 n/cm 2 (> 1 MeV) for zircaloy-2 and 5 × 10 19 n/cm 2 (> 1 MeV) for zircaloy-4 for low temperature, while no saturation was observed after elevated-temperature irradiation up to a fluence of 1.53 × 10 21 n/cm 2 (>1 MeV) . Low-temperature irradiation showed Δσ y ∞ . (φt) case1 3 below saturation while elevated-temperature irradiation showed Δσ y ∞ . (φt) 0.1 . The amount of irradiation-hardening decreased in zircaloy-4 as the pre-irradiation yield stress was increased either by increasing the amount of cold work or decreasing the grain size. The results are discussed in terms of recent results in electron microscopy of irradiated materials.
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