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Title: Primary water stress corrosion crack growth rates in Alloy 600 steam generator tubing

Abstract

Direct measurements of SCC crack growth rates have been used to determine the effects of changes in PWR primary water chemistry on the stress corrosion cracking behavior of Alloy 600 steam generator tubing. Reversing current DC potential measurement techniques have been adapted for use on thin walled tubing containing through-wall circumferential cracks. These techniques have been used to monitor crack rates in Alloy 600 tubing exposed to typical PWR primary water chemistries at 330{degrees}C. Crack growth rate studies, conducted under well defined stress intensity conditions, provide a sensitivity in the assessment of stress corrosion cracking susceptibility that is not possible using more traditional techniques. Preliminary studies have been conducted to determine the effects of B and Li concentrations on the stress corrosion crack growth rate of Alloy 600 tubing.

Authors:
;  [1];  [2]
  1. Westinghouse Science and Technology Center, Pittsburg, PA (United States)
  2. Westinghouse Nuclear Service Division, Pittsburgh, PA (United States)
Publication Date:
OSTI Identifier:
48088
Report Number(s):
CONF-910808-
TRN: 95:011519
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; INTERGRANULAR CORROSION; CRACK PROPAGATION; STEAM GENERATORS; TUBES; MONITORING; PWR TYPE REACTORS; WATER CHEMISTRY; LITHIUM HYDROXIDES; BORIC ACID; HYDROGEN; AQUEOUS SOLUTIONS

Citation Formats

Lott, R G, Jacko, R J, and Gold, R E. Primary water stress corrosion crack growth rates in Alloy 600 steam generator tubing. United States: N. p., 1992. Web.
Lott, R G, Jacko, R J, & Gold, R E. Primary water stress corrosion crack growth rates in Alloy 600 steam generator tubing. United States.
Lott, R G, Jacko, R J, and Gold, R E. 1992. "Primary water stress corrosion crack growth rates in Alloy 600 steam generator tubing". United States.
@article{osti_48088,
title = {Primary water stress corrosion crack growth rates in Alloy 600 steam generator tubing},
author = {Lott, R G and Jacko, R J and Gold, R E},
abstractNote = {Direct measurements of SCC crack growth rates have been used to determine the effects of changes in PWR primary water chemistry on the stress corrosion cracking behavior of Alloy 600 steam generator tubing. Reversing current DC potential measurement techniques have been adapted for use on thin walled tubing containing through-wall circumferential cracks. These techniques have been used to monitor crack rates in Alloy 600 tubing exposed to typical PWR primary water chemistries at 330{degrees}C. Crack growth rate studies, conducted under well defined stress intensity conditions, provide a sensitivity in the assessment of stress corrosion cracking susceptibility that is not possible using more traditional techniques. Preliminary studies have been conducted to determine the effects of B and Li concentrations on the stress corrosion crack growth rate of Alloy 600 tubing.},
doi = {},
url = {https://www.osti.gov/biblio/48088}, 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.

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