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

Abstract

Recent investigations of cracked steam generator tubes at nuclear power plants concluded that lead significantly contributed to cracking the Alloy 600 materials. In order to investigate the stress corrosion cracking (SCC) behavior of Alloy 690, slow strain rate tests (SSRT) and anodic polarization measurements were performed. The SSRTs were conducted in a lead-chloride solution (PbCl{sub 2}) and in a chloride but lead free solution (NaCl) at pH of 3 and 4.5 at 288 C. The anodic polarization measurements were carried out at 30 C using the same solutions as in SSRT. The SSRT results showed that Alloy 690 was susceptible to SCC in both solutions. In the lead chloride solution, cracking had slight dependence on lead concentration and pH. Cracking tend to increase with a higher lead concentration and a lower pH and was mainly intergranular and was to be a few tens to hundreds micrometers in length. In the chloride only solution, cracking was similar to the lead induced SCC. The results of anodic polarization measurement and electron probe micro analysis (EPMA) helped to understand lead induced SCC. Lead was a stronger active corrosive element but had a minor affect on cracking susceptibility of the alloy. While, chloride wasmore » quite different from lead effect to SCC. A possible mechanism of lead induced SCC of Alloy 690 was also discussed based on the test results.« less

Authors:
 [1];  [2]; ; ;  [3]
  1. Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
  2. Chonbuk Univ., Chonju (Korea, Republic of). Faculty of Technology
  3. Tohoku Univ., Sendai (Japan)
Publication Date:
OSTI Identifier:
203808
Report Number(s):
CONF-950816-
ISBN 1-877914-95-9; TRN: 96:009774
Resource Type:
Book
Resource Relation:
Conference: 7. international symposium on environmental degradation of materials in nuclear power plants: water reactors, Breckenridge, CO (United States), 6-10 Aug 1995; Other Information: PBD: 1995; Related Information: Is Part Of Seventh international symposium on environmental degradation of materials in nuclear power systems -- Water reactors: Proceedings and symposium discussions. Volume 1; Airey, G.; Andresen, P.; Brown, J. [eds.] [and others]; PB: 664 p.
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; LEAD; CORROSIVE EFFECTS; PWR TYPE REACTORS; STEAM GENERATORS; TUBES; STRESS CORROSION; CRACK PROPAGATION; INCONEL 690; CHLORIDES; EXPERIMENTAL DATA; SODIUM CHLORIDES; LEAD CHLORIDES

Citation Formats

Chung, K.K., Lim, J.K., Moriya, Shinichi, Watanabe, Yutaka, and Shoji, Tetsuo. Lead induced stress corrosion cracking of Alloy 690 in high temperature water. United States: N. p., 1995. Web.
Chung, K.K., Lim, J.K., Moriya, Shinichi, Watanabe, Yutaka, & Shoji, Tetsuo. Lead induced stress corrosion cracking of Alloy 690 in high temperature water. United States.
Chung, K.K., Lim, J.K., Moriya, Shinichi, Watanabe, Yutaka, and Shoji, Tetsuo. Sun . "Lead induced stress corrosion cracking of Alloy 690 in high temperature water". United States. doi:.
@article{osti_203808,
title = {Lead induced stress corrosion cracking of Alloy 690 in high temperature water},
author = {Chung, K.K. and Lim, J.K. and Moriya, Shinichi and Watanabe, Yutaka and Shoji, Tetsuo},
abstractNote = {Recent investigations of cracked steam generator tubes at nuclear power plants concluded that lead significantly contributed to cracking the Alloy 600 materials. In order to investigate the stress corrosion cracking (SCC) behavior of Alloy 690, slow strain rate tests (SSRT) and anodic polarization measurements were performed. The SSRTs were conducted in a lead-chloride solution (PbCl{sub 2}) and in a chloride but lead free solution (NaCl) at pH of 3 and 4.5 at 288 C. The anodic polarization measurements were carried out at 30 C using the same solutions as in SSRT. The SSRT results showed that Alloy 690 was susceptible to SCC in both solutions. In the lead chloride solution, cracking had slight dependence on lead concentration and pH. Cracking tend to increase with a higher lead concentration and a lower pH and was mainly intergranular and was to be a few tens to hundreds micrometers in length. In the chloride only solution, cracking was similar to the lead induced SCC. The results of anodic polarization measurement and electron probe micro analysis (EPMA) helped to understand lead induced SCC. Lead was a stronger active corrosive element but had a minor affect on cracking susceptibility of the alloy. While, chloride was quite different from lead effect to SCC. A possible mechanism of lead induced SCC of Alloy 690 was also discussed based on the test results.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Dec 31 00:00:00 EST 1995},
month = {Sun Dec 31 00:00:00 EST 1995}
}

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