In-situ monitoring of the corrosion behavior and impurity enrichment of steam generator tube materials under P W R secondary side thermal hydraulic and heat transfer conditions

Caitlin Huotilainen*, Essi Jäppinen, Tiina Ikäläinen, Seppo Peltonen, Timo Saario, Konsta Sipilä

*Corresponding author for this work

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    2 Citations (Scopus)

    Abstract

    A high temperature recirculation loop was developed to simulate secondary side boiling conditions in nuclear power plant steam generators under both normal operating conditions and during impurity, e.g. chloride, transients. In-situ electrochemical impedance spectroscopy was used to study the corrosion behavior and impurity enrichment of steam generator tubing materials as a function of boiling, flow rate and impurity levels. The effect of boiling can be clearly observed in the electrochemical response and in the shape of the pressure-temperature difference curve. Experimental results reveal that boiling contributes to both the surface area of the sample in contact with the solution and increases the corrosion rate. In addition, chloride injections resulted in a further increase in the corrosion rate and, when boiling is stopped, hideout return can be observed and quantified, thus enabling for the correlation between surface-chloride concentration and corrosion rate to be determined. Post-test material and oxide scale characterizations were performed using scanning electron microscope, energy-dispersive X-ray spectroscopy and glow-discharge optical emission spectroscopy after exposure to secondary side thermal hydraulic and heat transfer conditions, along with simulated impurity transients.

    Original languageEnglish
    Title of host publicationNineteenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
    PublisherAmerican Nuclear Society (ANS)
    Pages1181-1190
    Number of pages10
    Editioncd-rom
    ISBN (Electronic)978-0-89448-765-1
    Publication statusPublished - 2019
    MoE publication typeA4 Article in a conference publication
    Event19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019 - Boston, United States
    Duration: 18 Aug 201922 Aug 2019

    Conference

    Conference19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019
    Abbreviated titleENVDEG 2019
    Country/TerritoryUnited States
    CityBoston
    Period18/08/1922/08/19

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