In nuclear power plants, inner surface of reactor pressure vessel, which is made of low-alloy steel, is cladded by austenitic stainless steel to improve corrosion resistance of vessel. In an evaluation of fatigue crack propagation behavior at J-welding portions of bottom mounted instrumentation in reactor pressure vessel, crack propagation crossing dissimilar materials interface between base metal of low-alloy steel and stainless steel cladding is assumed. Fatigue crack growth rate of the cladding is predicted to be captured by that of the base metal because thickness of the cladding is very thin compared that of the base metal. In this study, fatigue crack propagation analyses of cladded plates under cyclic loading were performed using XFEM, which can model crack independently of finite elements, as a preliminary study for crack propagation analyses considering dissimilar materials interface.
Evaluation of Fatigue Crack Propagation Behavior Crossing Interface in Cladded Plates
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Nagai, M, Murai, K, Nagashima, T, & Miura, N. "Evaluation of Fatigue Crack Propagation Behavior Crossing Interface in Cladded Plates." Proceedings of the ASME 2017 Pressure Vessels and Piping Conference. Volume 6A: Materials and Fabrication. Waikoloa, Hawaii, USA. July 16–20, 2017. V06AT06A001. ASME. https://doi.org/10.1115/PVP2017-65347
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