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Title: Characteristics of lead induced stress corrosion cracking of alloy 690 in high temperature

Abstract

Slow strain rate tests (SSRT) were conducted on alloy 690 in various lead chloride solutions and metal lead added to 100 ppm chloride solution at 288 C. The corrosion potential (rest potential) for the alloy was measured with SSRT tests. The cracking was observed by metallographic examination and electron probe micro analyzer. Also, the corrosion behavior of the alloy was evaluated by anodic polarized measurement at 30 C. Resulting from the tests, cracking was characterized by cracking behavior, crack length and crack growth rate, and lead effects on cracking. The cracking was mainly intergranular in mode, approximately from 60 um to 450 um in crack length, and approximately 10{sup {minus}6} to 10{sup {minus}7} mmS-1 in crack velocity. The cracking was evaluated through the variation the corrosion potential in potential-time and lead behavior during SSRTs. The lead effect in corrosion was evaluated through active to passive transition behavior in anodic polarized curves. The corrosion reactions in the cracking region were confirmed by electron probe microanalysis. Alloy 690 is used for steam generation tubes in pressurized water reactors.

Authors:
 [1];  [2]; ;  [3]
  1. Korea Inst. of Nuclear Safety, Taejon (Korea, Republic of)
  2. Chonbuk National Univ., Chonju (Korea, Republic of)
  3. Tohoku Univ., Sendai (Japan). Research Inst. for Fracture Technology
Publication Date:
OSTI Identifier:
367702
Report Number(s):
CONF-960389-
TRN: IM9640%%448
Resource Type:
Book
Resource Relation:
Conference: National Association of Corrosion Engineers (NACE) annual corrosion conference and exposition: water and waste water industries, Denver, CO (United States), 24-29 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of Corrosion/96 conference papers; PB: [6615] p.
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; REACTOR MATERIALS; INCONEL 690; STRESS CORROSION; CRACK PROPAGATION; LEAD CHLORIDES; CORROSIVE EFFECTS; EXPERIMENTAL DATA; INTERGRANULAR CORROSION

Citation Formats

Chung, K.K., Lim, J.K., Watanabe, Yutaka, and Shoji, Tetsuo. Characteristics of lead induced stress corrosion cracking of alloy 690 in high temperature. United States: N. p., 1996. Web.
Chung, K.K., Lim, J.K., Watanabe, Yutaka, & Shoji, Tetsuo. Characteristics of lead induced stress corrosion cracking of alloy 690 in high temperature. United States.
Chung, K.K., Lim, J.K., Watanabe, Yutaka, and Shoji, Tetsuo. Tue . "Characteristics of lead induced stress corrosion cracking of alloy 690 in high temperature". United States. doi:.
@article{osti_367702,
title = {Characteristics of lead induced stress corrosion cracking of alloy 690 in high temperature},
author = {Chung, K.K. and Lim, J.K. and Watanabe, Yutaka and Shoji, Tetsuo},
abstractNote = {Slow strain rate tests (SSRT) were conducted on alloy 690 in various lead chloride solutions and metal lead added to 100 ppm chloride solution at 288 C. The corrosion potential (rest potential) for the alloy was measured with SSRT tests. The cracking was observed by metallographic examination and electron probe micro analyzer. Also, the corrosion behavior of the alloy was evaluated by anodic polarized measurement at 30 C. Resulting from the tests, cracking was characterized by cracking behavior, crack length and crack growth rate, and lead effects on cracking. The cracking was mainly intergranular in mode, approximately from 60 um to 450 um in crack length, and approximately 10{sup {minus}6} to 10{sup {minus}7} mmS-1 in crack velocity. The cracking was evaluated through the variation the corrosion potential in potential-time and lead behavior during SSRTs. The lead effect in corrosion was evaluated through active to passive transition behavior in anodic polarized curves. The corrosion reactions in the cracking region were confirmed by electron probe microanalysis. Alloy 690 is used for steam generation tubes in pressurized water reactors.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Oct 01 00:00:00 EDT 1996},
month = {Tue Oct 01 00:00:00 EDT 1996}
}

Book:
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