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      • KCI등재

        Tensile and impact toughness properties of various regions of dissimilar joints of nuclear grade steels

        K. Karthick,S. Malarvizhi,V. Balasubramanian,S.A. Krishnan,G. Sasikala,Shaju K. Albert 한국원자력학회 2018 Nuclear Engineering and Technology Vol.50 No.1

        Modified 9Cr-1Mo ferritic steel is a preferred material for steam generators in nuclear power plants fortheir creep strength and good corrosion resistance. Austenitic stainless steels, such as type 316LN, areused in the high temperature segments such as reactor pressure vessels and primary piping systems. So,the dissimilar joints between these materials are inevitable. In this investigation, dissimilar joints werefabricated by the Shielded Metal Arc Welding (SMAW) process with Inconel 82/182 filler metals. Thenotch tensile properties and Charpy V-notch impact toughness properties of various regions of dissimilarmetal weld joints (DMWJs) were evaluated as per the standards. The microhardness distribution acrossthe DMWJs was recorded. Microstructural features of different regions were characterized by optical andscanning electron microscopy. Inhomogeneous notch tensile properties were observed across theDMWJs. Impact toughness values of various regions of the DMWJs were slightly higher than the prescribedvalue. Formation of a carbon-enriched hard zone at the interface between the ferritic steel andthe buttering material enhanced the notch tensile properties of the heat-affected-zone (HAZ) of P91. Thecomplex microstructure developed at the interfaces of the DMWJs was the reason for inhomogeneousmechanical properties

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