journal article·1998-07-01

Mechanism of Lead-Induced Stress Corrosion Cracking of Nickel-Based Alloys in High-Temperature Water

T. Sakai, N. Nakagomi, T. Kikuchi, K. Aoki, F. Nakayasu, K. Yamakawa

Corrosion· Volume 54· Issue 7
Publisher page

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.
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Research context

OpenAlex topics: Nuclear Materials and Properties · Corrosion Behavior and Inhibition · Hydrogen embrittlement and corrosion behaviors in metals

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

Affiliations

*Nuclear Fuel Industries, Ltd., 950 Chaza-Noda, Kumatori-cho Sennan-gun, Osaka, 590-0451, Japan.

**University of Osaka Prefecture, 1-1 Gakuen-cho, Sakai-city, Osaka, 599-8531, Japan.

References (10)

Show source-provided references
1. Examination of Tubes Removed from St. Lucie Unit 1 and Investigation of Causes of the Corrosion
2. Some Considerations About the Possible Mechanisms of Lead-Assisted Stress Corrosion Cracking of Steam Generator Tubing
3. Accelerated IGA/SCC Testing of Alloy 600 in Contaminated PWR Environments
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5. Lead-Induced Stress Corrosion Cracking of Alloy 600 and 690 in High-Temperature Water
6. Influence of Lead Contamination on the Stress Corrosion Resistance of Nickel Alloys
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8. Sakai · Corrosion · 1992 · 48 · 73410.5006/1.3315995 ↗
9. The Causes and Remedial Measures of Steam Generator Tube Intergranular Attack in Japanese PWR
10. Study on Lead-Induced Stress Corrosion Cracking of Steam Generator Tubing Under AVT Water Chemistry Conditions