scispace - formally typeset
Journal ArticleDOI

Oxidation products of INCONEL alloys 600 and 690 in pressurized water reactor environments and their role in intergranular stress corrosion cracking

Reads0
Chats0
TLDR
In this article, a crack initiation mechanism was proposed to explain crack initiation and propagation in INCONEL alloy 600 along the grain boundaries, where Cr2O3 has formed from the leaching of Cr from the matrix, leaving behind a porous Ni-rich region.
Abstract
In this work, thermodynamic arguments for the stability of Ni and Cr compounds developed under pressurized water reactor environments (\(P_{H_2 O} \) and\(P_{H_2 } \)) were experimentally tested. A mechanism is proposed to explain crack initiation and propagation alloy 600 along the grain boundaries, where Cr2O3 has formed from the leaching of Cr from the matrix, leaving behind a porous Ni-rich region. The mechanism is based on the thermodynamic potential for the transformation of a protective NiO surface layer into an amorphous nonprotective Ni(OH)2 gel. This gel would also form along the grain boundaries and when hydrogenated steam reaches the porous Ni-rich regions. Crack initiation is then favored by tensile stressing of the grain boundary regions, which can easily rupture the gelatinous film. The leaching of matrix Cr to form nonprotective CrOOH gel at the crack tip followed by the exposure of fresh porous Ni to the environment could explain crack propagation in INCONEL alloy 600. The proposed crack initiation mechanism is not expected to occur in alloy 690 where a protective Cr2O3 film covers the entire metal surface. However, crack propagation along the grain boundaries in alloy 600 and precracked alloy 690 is expected to be active as hydroxide-forming reactions weaken the boundaries.

read more

Citations
More filters
Journal ArticleDOI

Influence of dissolved oxygen on oxide films of Alloy 690TT with different surface status in simulated primary water

TL;DR: In this article, the growth mechanism of the oxide film was discussed, and three layers of Alloy 690 were formed; the outmost layer with dispersed big oxide particles; the intermediated layer with loose sheet-like or needle-like oxides and the inner layer with incompact cellular oxides, which were lack of protectiveness.
Journal ArticleDOI

Laser cladding of Inconel 690 on Inconel 600 superalloy for corrosion protection in nuclear applications

TL;DR: In this paper, the results of applying a 3 mm thick cladding layer by laser melting Inconel 690 powder on top of a 10 mm thick plate of Inconels 600 alloy substrate were reported.
Journal ArticleDOI

Effect of dissolved hydrogen on corrosion of Inconel Alloy 600 in high temperature hydrogenated water

TL;DR: In this article, the effect of dissolved hydrogen (DH) levels on the Ni/NiO phase transition was investigated by employing electrochemical and exposure experiments, and the results showed that increasing DH in water decreased the thickness and the ionic defect transport resistance of the oxide film, in conjunction with the increase of Cr- but decrease of Ni-concentrations in the oxide.
Journal ArticleDOI

Effect of electropolishing on corrosion of nuclear grade 316L stainless steel in deaerated high temperature water

TL;DR: In this paper, the effect of change in surface composition and microstructure by electropolishing on corrosion of nuclear grade 316L stainless steel in deaerated high temperature water was investigated.
Journal ArticleDOI

Influence of humidity on high temperature oxidation of Inconel 600 alloy: Oxide layers and residual stress study

TL;DR: In this paper, the influence of humidity on high temperature oxidation of Inconel 600 alloy was analyzed by using X-ray diffraction method in each of two oxide phases, simultaneously and the oxide surface morphology, cross-section microstructure and the chemical composition of the oxide layers were determined by FEG-SEM (Field Emission Gun Scanning Electron Microscope) observation and FEGSEM EDS (Energy-dispersive Xray spectroscopy).
References
More filters
Journal ArticleDOI

High-Resolution Characterization of Intergranular Attack and Stress Corrosion Cracking of Alloy 600 in High-Temperature Primary Water

TL;DR: In this article, U-bend samples tested in 330°C pressurized water reactor water were characterized by analytical tran...Intergranular (IG) attack regions and stress corrosion cracks in Alloy 600 (UNS N06600).
Journal ArticleDOI

Oxidation Mechanism of Ni—20Cr Foils and Its Relation to the Oxide-Scale Microstructure

TL;DR: In this paper, the oxidation behavior of Ni-20Cr foils of 100- and 200-μm thickness was studied in air between 500 and 900°C and the morphology, microstructure, and composition of the oxide layers were determined by scanning and transmission electron microscopies.
Journal ArticleDOI

Influence of Dissolved Hydrogen on Structure of Oxide Film on Alloy 600 Formed in Primary Water of Pressurized Water Reactors

TL;DR: In this paper, structural analysis of oxide films formed under four different dissolved hydrogen (DH) conditions in simulated primary water of PWR was carried out using a grazing incidence X-ray diffractometer (GIXRD), a scanning electron microscope (SEM) and a transmission electron microscopy (TEM).
Journal ArticleDOI

X‐Ray Photoelectron Studies of the Aqueous Oxidation of Inconel‐600 Alloy

TL;DR: Aqueous oxidation of the nickel-based alloy Inconel-600 has been studied using x-ray photoelectron spectroscopy as the primary means of determining the elemental composition and chemistry of the surface films produced.
Journal ArticleDOI

2000 F.N. Speller Award Lecture: Stress Corrosion Cracking in Pressurized Water Reactors Interpretation, Modeling, and Remedies

P. M. Scott
- 01 Aug 2000 - 
TL;DR: The aging of water-cooled and moderated nuclear steam supply systems inevitably has given rise to many material corrosion problems of which stress corrosion cracking (SCC) is one of the most common as mentioned in this paper.
Related Papers (5)