LAUSR

Abstract A 100 MW AP1000 Reactor was considered and welding processes were employed in joining of the main feed water nozzle, in primary circuit of nuclear reactors were simulated by means of finite element method. Distribution and magnitude of the residual stresses created by thermal processes including cladding inside the nozzle, buttering prior to dissimilar welding, heat treatment and dissimilar welding of the safe-end austenitic stainless steel to the nozzle ferritic steel were investigated. Norton-Bailey creep model was used for heat treatment simulations. Experimental results obtained in previous studies and residual stress measurements were applied for verification of the developed model. It was revealed that residual stresses after cladding were approximately equal to yield strength of the materials. Also, buttering led to reduction of residual stresses in the nozzle free end. Heat treatment decreased residual stresses in the base metal significantly; whereas, it had minor effects on those in the cladding layer. Besides, circumferential residual stresses were invariably tensile at inner and outer surfaces of the joint. Further discussions were provided to explain the obtained result.