The Atucha II nuclear power plant is a pressurized heavy water reactor (PHWR) being constructed in Argentina. The original plant was designed by Kraftwerk Union (KWU) in the 1970’s using the German methodology of break preclusion. The plant construction was halted for several decades, but a recent need for power was the driver for restarting the construction. Welding residual stresses in nuclear power plant piping can lead to cracking concerns later in the life of the plant, especially for stress-corrosion cracking. Hence, understanding the residual stress distribution from welding is important to evaluate the reliability of pipe and nozzle joints with welds. In this paper, a large-diameter reactor pressure vessel (RPV) hot-leg nozzle was analyzed. This is a nozzle from Atucha II nuclear power plant in Argentina. The main piping material is 20MnMoNi55 with Tenacito 65R weld metal, and inner diameter (ID) welded cladding at the girth weld locations is made of 309L. The special materials and weld geometry will lead interesting welding residual stress fields. In addition, postweld heat treatment (PWHT) of the girth welds and its boundary conditions could also play an important role in determining welding residual stress fields at the plant’s normal operating conditions. Sensitivity analyses were conducted and the technical observations and comments are provided.
Welding Residual Stress in a Large Diameter Nuclear Reactor Pressure Vessel Nozzle
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the Journal of Pressure Vessel Technology. Manuscript received March 21, 2012; final manuscript received October 20, 2012; published online March 18, 2013. Assoc. Editor: Somnath Chattopadhyay.
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Zhang, T., Brust, F. W., Wilkowski, G., Xu, H., Betervide, A. A., and Mazzantini, O. (March 18, 2013). "Welding Residual Stress in a Large Diameter Nuclear Reactor Pressure Vessel Nozzle." ASME. J. Pressure Vessel Technol. April 2013; 135(2): 021208. https://doi.org/10.1115/1.4007961
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