Stress Corrosion Cracking Behavior of Alloy 182 Weld in Pressurized Water Reactor Primary Water Environment at 325°C

• Published in: Corrosion (Houston, Tex.) Tex.), 2011-08, Vol.67 (8), p.C1
• Main Authors: LIMA, L. I. L, SCHVARTZMAN, M. M. A. M, FIGUEIREDO, C. A, BRACARENSE, A. Q
• Format: Article
• Language: English
• Subjects: Alloys; Applied sciences; Chemistry; Corrosion; Corrosion environments; Corrosion resistance; Corrosion tests; Exact sciences and technology; Growth rate; Joining, thermal cutting: metallurgical aspects; Materials science; Metals. Metallurgy; Reactors; Residual stress; Scanning electron microscopy; Welding
• ISSN: 0010-9312; 1938-159X

The weld used to connect two different metals is known as a dissimilar metal weld (DMW). In nuclear power plants, this weld is used to join stainless steel to low-alloy steel components in the nuclear pressurized water reactor (PWR). The most common weld metal is Alloy 182 (UNS W86182). Originally selected for its high corrosion resistance, it exhibited, after a long operation period, susceptibility to stress corrosion cracking (SCC) in PWR. The goal of this work was to study the electrochemical corrosion behavior and SCC susceptibility of Alloy 182 weld in PWR primary water containing 25 cm^sup 3^ and 50 cm^sup 3^ H^sub 2^/kg H2O at standard temperature and pressure (STP). For this purpose, slow strain rate tensile (SSRT) tests and potentiodynamic polarization measurements were carried out. Scanning electron microscopy (SEM) with energy-dispersive spectrometry (EDS) was used to evaluate fracture morphology and determine the oxide layer chemical composition and morphology. The results indicated that at 325°C Alloy 182 weld is more susceptible to SCC at 25 cm^sup 3^ (STP) H^sub 2^/kg H2O and the increase of dissolved hydrogen decreased the crystal size of the oxide layer. [PUBLICATION ABSTRACT]