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The concrete biological shields (CBSs) of light water reactors are affected by neutron and gamma irradiation at high radiation doses, resulting in the degradation of the concrete’s material properties. Several studies in the literature focused on evaluating both the expansion of aggregate-forming minerals and the resulting loss of mechanical properties. Modeling efforts have been carried out to predict theradiation-induced volumetric expansion (RIVE) and damage using different numerical methods such as the finite element method or fast-Fourier transform (FFT).
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Dissimilar metal welds (DMWs) are commonly used in the pressure vessel nozzle to safe-end weld between the ferritic low-alloy steels (LAS) and the austenitic stainless steels (SS), using a nickel-base filler metal. The complex DMW interface consists of different microstructural regions including, for instance, the heat-affected zone (HAZ), carbon-depleted zone (CDZ), carbon build-up at fusion boundary, partially melted zone (PMZ) and carbide precipitation zone. There is still knowledge lacking on the microstructural characteristics of the interface of DMWs upon post-weld heat treatment (PWHT). DMWs are potential concerns regarding the structural integrity of the nuclear power systems. In particular, the LAS/nickel-base alloy weld metal interface is known to develop a local strength mismatch upon PWHT and during long-term ageing. A significant chemical composition gradient, especially in terms of carbon (C) and chromium (Cr) associated with a complex microstructure have been observed to form at the interfaces. The different welding orientation, heat transfer and PWHT can result in different microstructure and mechanical properties.