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Title: Mechanism of lead-induced stress corrosion cracking of nickel-based alloys in high-temperature water

Abstract

A study was undertaken to better understand the lead-induced corrosion mechanism of nickel-based alloys used for steam generator tubing materials (alloys 600 and 690 [UNS N06600 and N06690]) in pressurized-water reactor (PWR) plants. Electrochemical measurements (corrosion potential and polarization measurements) and constant extension rate tests (CERT) of tubing materials were performed in lead-contaminated environments. Results of electrochemical measurements showed lead did not raise the corrosion potential but did increase the anodic polarization current in the passivity region, which indicated degradation of the passive oxide film. CERT results showed alloy 690 had better corrosion resistance than alloy 600, which was in good agreement with the lower intensity of the anodic current. The mechanism of lead-induced corrosion was proposed as disruption of the oxide film of the alloys as a result of the incorporation of lead.

Authors:
; ; ; ;  [1];  [2]
  1. Nuclear Fuel Industries, Ltd., Osaka (Japan)
  2. Univ. of Osaka, Sakai, Osaka (Japan)
Publication Date:
Sponsoring Org.:
USDOE
OSTI Identifier:
634553
Resource Type:
Journal Article
Journal Name:
Corrosion
Additional Journal Information:
Journal Volume: 54; Journal Issue: 7; Other Information: PBD: Jul 1998
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; STRESS CORROSION; FRACTURE PROPERTIES; NICKEL BASE ALLOYS; PWR TYPE REACTORS; LEAD; METALLURGICAL EFFECTS; ELECTROCHEMISTRY; CRACK PROPAGATION; EXPERIMENTAL DATA; STEAM GENERATORS; TUBES

Citation Formats

Sakai, T, Nakagomi, N, Kikuchi, T, Aoki, K, Nakayasu, F, and Yamakawa, K. Mechanism of lead-induced stress corrosion cracking of nickel-based alloys in high-temperature water. United States: N. p., 1998. Web. doi:10.5006/1.3284879.
Sakai, T, Nakagomi, N, Kikuchi, T, Aoki, K, Nakayasu, F, & Yamakawa, K. Mechanism of lead-induced stress corrosion cracking of nickel-based alloys in high-temperature water. United States. https://doi.org/10.5006/1.3284879
Sakai, T, Nakagomi, N, Kikuchi, T, Aoki, K, Nakayasu, F, and Yamakawa, K. 1998. "Mechanism of lead-induced stress corrosion cracking of nickel-based alloys in high-temperature water". United States. https://doi.org/10.5006/1.3284879.
@article{osti_634553,
title = {Mechanism of lead-induced stress corrosion cracking of nickel-based alloys in high-temperature water},
author = {Sakai, T and Nakagomi, N and Kikuchi, T and Aoki, K and Nakayasu, F and Yamakawa, K},
abstractNote = {A study was undertaken to better understand the lead-induced corrosion mechanism of nickel-based alloys used for steam generator tubing materials (alloys 600 and 690 [UNS N06600 and N06690]) in pressurized-water reactor (PWR) plants. Electrochemical measurements (corrosion potential and polarization measurements) and constant extension rate tests (CERT) of tubing materials were performed in lead-contaminated environments. Results of electrochemical measurements showed lead did not raise the corrosion potential but did increase the anodic polarization current in the passivity region, which indicated degradation of the passive oxide film. CERT results showed alloy 690 had better corrosion resistance than alloy 600, which was in good agreement with the lower intensity of the anodic current. The mechanism of lead-induced corrosion was proposed as disruption of the oxide film of the alloys as a result of the incorporation of lead.},
doi = {10.5006/1.3284879},
url = {https://www.osti.gov/biblio/634553}, journal = {Corrosion},
number = 7,
volume = 54,
place = {United States},
year = {Wed Jul 01 00:00:00 EDT 1998},
month = {Wed Jul 01 00:00:00 EDT 1998}
}