Welding Residual Stress in a Large Diameter Nuclear Reactor Pressure Vessel Nozzle
Author:
Zhang Tao1, Brust Frederick W., Wilkowski Gery, Xu Heqin2, Betervide Alfredo A., Mazzantini Oscar3
Affiliation:
1. e-mail: 2. Engineering Mechanics Corporation
of Columbus, 3518 Riverside Dr. - Suite 202, Columbus, OH 43221 3. Nucleoelectrica Argentina S. A., Buenos Aires 2806, Argentina
Abstract
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.
Publisher
ASME International
Subject
Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality
Reference12 articles.
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