skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Lead-induced stress corrosion cracking of Alloy 600 and 690 in high temperature water

Abstract

Lead is one of the potential contributing impurities to the degradation of PWR steam generator tubing. Recent laboratory testing has shown that lead is a corrosive material for Alloy 600 steam generator tubing. However, it is still unknown how lead influences the corrosion of steam generator tubing, including the effect of lead concentration, solution pH, stress level and material characteristics. In this study, two kinds of experiments were performed. One was to investigate the thin film characteristic and selectively dissolved base metal elements of Alloy 600MA in high temperature solutions of different lead concentrations and pH. The other investigated the dependency of degradation of Alloy 600MA and Alloy 690TT on lead concentration and stress level in mild acidic environment, at 340{degrees}C for 2500 hrs. It was firstly demonstrated that lead-enhanced selective dissolution of nickel from alloy base metal, as a result of electrochemical reaction between lead and nickel, might cause the initiation and propagation of corrosion. Secondly, we showed that Alloy 690TT, generally very corrosion resistant material, also suffered from Pb-induced corrosion. The difference of the lead-induced stress corrosion morphology of Alloy 600MA and Alloy 690TT was also clarified.

Authors:
; ; ; ;  [1]
  1. Nuclear Fuel Industries, Ltd., Osaka (Japan)
Publication Date:
OSTI Identifier:
48112
Report Number(s):
CONF-910808-
TRN: 95:011546
Resource Type:
Conference
Resource Relation:
Conference: 5. international symposium on environmental degradation of materials in nuclear power systems - water reactors, Monterey, CA (United States), 25-29 Aug 1991; Other Information: PBD: 1992; Related Information: Is Part Of Proceedings of the fifth international symposium on environmental degradation of materials in nuclear power systems - water reactors; PB: 995 p.
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 36 MATERIALS SCIENCE; INCONEL 600; STRESS CORROSION; INCONEL 690; STEAM GENERATORS; TUBES; PWR TYPE REACTORS; SECONDARY COOLANT CIRCUITS; WATER CHEMISTRY; LEAD

Citation Formats

Sakai, T., Senjuh, T., Aoki, K., Shigemitsu, T., and Kishi, Y.. Lead-induced stress corrosion cracking of Alloy 600 and 690 in high temperature water. United States: N. p., 1992. Web.
Sakai, T., Senjuh, T., Aoki, K., Shigemitsu, T., & Kishi, Y.. Lead-induced stress corrosion cracking of Alloy 600 and 690 in high temperature water. United States.
Sakai, T., Senjuh, T., Aoki, K., Shigemitsu, T., and Kishi, Y.. Thu . "Lead-induced stress corrosion cracking of Alloy 600 and 690 in high temperature water". United States. doi:.
@article{osti_48112,
title = {Lead-induced stress corrosion cracking of Alloy 600 and 690 in high temperature water},
author = {Sakai, T. and Senjuh, T. and Aoki, K. and Shigemitsu, T. and Kishi, Y.},
abstractNote = {Lead is one of the potential contributing impurities to the degradation of PWR steam generator tubing. Recent laboratory testing has shown that lead is a corrosive material for Alloy 600 steam generator tubing. However, it is still unknown how lead influences the corrosion of steam generator tubing, including the effect of lead concentration, solution pH, stress level and material characteristics. In this study, two kinds of experiments were performed. One was to investigate the thin film characteristic and selectively dissolved base metal elements of Alloy 600MA in high temperature solutions of different lead concentrations and pH. The other investigated the dependency of degradation of Alloy 600MA and Alloy 690TT on lead concentration and stress level in mild acidic environment, at 340{degrees}C for 2500 hrs. It was firstly demonstrated that lead-enhanced selective dissolution of nickel from alloy base metal, as a result of electrochemical reaction between lead and nickel, might cause the initiation and propagation of corrosion. Secondly, we showed that Alloy 690TT, generally very corrosion resistant material, also suffered from Pb-induced corrosion. The difference of the lead-induced stress corrosion morphology of Alloy 600MA and Alloy 690TT was also clarified.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Dec 31 00:00:00 EST 1992},
month = {Thu Dec 31 00:00:00 EST 1992}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: