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Due to the strength, ductility, fracture toughness, corrosion resistance and especially the coefficient of thermal expansion, which is between stainless steel and low alloy steel, Ni-based alloys are used as weld metals in BWR and ABWR internals. Ni-based alloys with high chromium (Cr) concentration, such as Alloy 52 (Cr: 28-31.5 wt.%), Alloy 52i (Cr: 26-28 wt.%) and so on are expected to have higher SCC resistance than 182 (Cr: 13-17 wt.%) and Alloy 82 (Cr: 18-22 wt.%) in BWR environment.
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The austenitic Ni-base Alloy 600 has been extensively used as structural material in primary water reactors (PWR). Despite good resistance against general corrosion in water-cooled nuclear power reactors, the material has been susceptible to stress corrosion cracking (SCC). These observations have led to ongoing discussions of the underlying embrittlement mechanism(s). Internal oxidation of the grain boundary (GB) at typical operating temperatures is one such mechanism, although debate continues on the exact mechanisms at play.