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51316-7166-Corrosion of Nickel Alloys for Steam Generator Tubing of Pressurized Water Reactors

Fe-Cr-Ni alloys such as alloys 600 625 690 and 800 are used in steam generator tubing of nuclear power reactors. Precipitation of impurities on the steam generator tubing can lead to fouling and formation of deposits yielding a partially occluded metal surface.  In this work the crevice corrosion susceptibility of these alloys is analyzed. 

Product Number: 51316-7166-SG
ISBN: 7166 2016 CP
Author: Martin Rodriguez
Publication Date: 2016
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Fe-Cr-Ni alloys such as alloys 600 625 690 and 800 are used in steam generator tubing of nuclear power reactors due to their high mechanical strength and corrosion resistance at high temperature. Under operating conditions precipitation of impurities on the steam generator tubing can lead to fouling and formation of deposits yielding a partially occluded metal surface. In this work the crevice corrosion susceptibility of these alloys is analyzed. Crevice corrosion was studied in 1 M 0.1 M and 0.01 M NaCl solutions at 30 °C 60 °C and 90 °C and atmospheric pressure using artificially creviced specimens. Alloy specimens were polarized potentiodynamically up to 300 µA and held at that current for 2 hours; then the potential scan was reversed until reaching the alloy repassivation.All the alloys except alloy 625 suffered crevice corrosion. Test reproducibility was higher under more aggressive conditions (i.e. higher temperature and chloride concentration). The repassivation potential decreased with increasing temperature and chloride concentration indicating higher crevice corrosion susceptibility.Electrochemical impedance techniques were used to estimate corrosion rates and to characterize the passive oxide layer through the Mott-Schottky analysis. Tested alloys showed an n- to p-type transition with increasing potentia

 

Keywords: downloadable, UNS N06690, UNS N06600, UNS N08800, temperature, chloride, localized corrosion

 

Fe-Cr-Ni alloys such as alloys 600 625 690 and 800 are used in steam generator tubing of nuclear power reactors due to their high mechanical strength and corrosion resistance at high temperature. Under operating conditions precipitation of impurities on the steam generator tubing can lead to fouling and formation of deposits yielding a partially occluded metal surface. In this work the crevice corrosion susceptibility of these alloys is analyzed. Crevice corrosion was studied in 1 M 0.1 M and 0.01 M NaCl solutions at 30 °C 60 °C and 90 °C and atmospheric pressure using artificially creviced specimens. Alloy specimens were polarized potentiodynamically up to 300 µA and held at that current for 2 hours; then the potential scan was reversed until reaching the alloy repassivation.All the alloys except alloy 625 suffered crevice corrosion. Test reproducibility was higher under more aggressive conditions (i.e. higher temperature and chloride concentration). The repassivation potential decreased with increasing temperature and chloride concentration indicating higher crevice corrosion susceptibility.Electrochemical impedance techniques were used to estimate corrosion rates and to characterize the passive oxide layer through the Mott-Schottky analysis. Tested alloys showed an n- to p-type transition with increasing potentia

 

Keywords: downloadable, UNS N06690, UNS N06600, UNS N08800, temperature, chloride, localized corrosion

 

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