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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.
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Stress corrosion cracking (SCC) has been observed for over six decades in light water reactors structural components, with wide variations in the rate of SCC initiation and crack growth. Newer materials have been adopted in the last three decades, primarily the ~30% Cr Alloy 690 (UNS N06690) and its weld metals, Alloy 52 (UNS W86052) and Alloy 152 (UNS W86152). These materials were initially viewed as immune to SCC, but are now recognized to be susceptibility to SCC, and can exhibit high growth rates in some conditions.