Corrosion Studies of Candidate Materials for European HPLWR

Sami Penttilä, Aki Toivonen, Liisa Heikinheimo, Radek Novotny

    Research output: Contribution to journalArticleScientificpeer-review

    10 Citations (Scopus)

    Abstract

    The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; however, the material requirements for HPLWR offer challenges because of the extreme operating temperatures and pressures. Consequently, general corrosion rates were studied in water at 300 to 650°C at supercritical pressure using weight gain measurements. Oxide thicknesses were determined from cross-section samples. The compositions of the oxide layers were analyzed using scanning electron microscopy in conjuction with energy dispersive spectroscopy. The surface layers of selected samples were analyzed also by X-ray diffraction. The test matrix included ten materials from four alloy classes: ferritic/martensitic steels, oxide dispersion strengthened (ODS) steels, austenitic stainless steels, and nickel-base alloys. A high oxidation resistance was seen in Ni-base alloy 625, austenitic stainless steels with high Cr content (>18 wt% Cr), and an ODS steel containing 20% Cr at all applied test temperatures (300 to 650°C). The oxidation rates of austenitic stainless steels with lower Cr content, 15 to 18%, increase considerably at temperatures >500°C. The oxidation rates of 9% Cr ODS steels were moderate or high at all temperatures. Ferritic/martensitic steels showed high oxidation rates at all temperatures.
    Original languageEnglish
    Pages (from-to)261-271
    Number of pages11
    JournalNuclear Technology
    Volume170
    Issue number1
    DOIs
    Publication statusPublished - 2010
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Light water reactors
    Corrosion
    Austenitic stainless steel
    Oxides
    Martensitic steel
    Ferritic steel
    Oxidation
    Steel
    Temperature
    Gain measurement
    Oxidation resistance
    Weighing
    Corrosion rate
    Energy dispersive spectroscopy
    Nickel
    X ray diffraction
    Scanning electron microscopy
    Chemical analysis
    Water

    Keywords

    • SCWR
    • general corrosion
    • candidate alloys

    Cite this

    Penttilä, Sami ; Toivonen, Aki ; Heikinheimo, Liisa ; Novotny, Radek. / Corrosion Studies of Candidate Materials for European HPLWR. In: Nuclear Technology. 2010 ; Vol. 170, No. 1. pp. 261-271.
    @article{c0de19e792dc47cb8b19526ec46eacea,
    title = "Corrosion Studies of Candidate Materials for European HPLWR",
    abstract = "The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; however, the material requirements for HPLWR offer challenges because of the extreme operating temperatures and pressures. Consequently, general corrosion rates were studied in water at 300 to 650°C at supercritical pressure using weight gain measurements. Oxide thicknesses were determined from cross-section samples. The compositions of the oxide layers were analyzed using scanning electron microscopy in conjuction with energy dispersive spectroscopy. The surface layers of selected samples were analyzed also by X-ray diffraction. The test matrix included ten materials from four alloy classes: ferritic/martensitic steels, oxide dispersion strengthened (ODS) steels, austenitic stainless steels, and nickel-base alloys. A high oxidation resistance was seen in Ni-base alloy 625, austenitic stainless steels with high Cr content (>18 wt{\%} Cr), and an ODS steel containing 20{\%} Cr at all applied test temperatures (300 to 650°C). The oxidation rates of austenitic stainless steels with lower Cr content, 15 to 18{\%}, increase considerably at temperatures >500°C. The oxidation rates of 9{\%} Cr ODS steels were moderate or high at all temperatures. Ferritic/martensitic steels showed high oxidation rates at all temperatures.",
    keywords = "SCWR, general corrosion, candidate alloys",
    author = "Sami Penttil{\"a} and Aki Toivonen and Liisa Heikinheimo and Radek Novotny",
    note = "Project code: 20062",
    year = "2010",
    doi = "10.13182/NT10-A9463",
    language = "English",
    volume = "170",
    pages = "261--271",
    journal = "Nuclear Technology",
    issn = "0029-5450",
    publisher = "American Nuclear Society ANS",
    number = "1",

    }

    Corrosion Studies of Candidate Materials for European HPLWR. / Penttilä, Sami; Toivonen, Aki; Heikinheimo, Liisa; Novotny, Radek.

    In: Nuclear Technology, Vol. 170, No. 1, 2010, p. 261-271.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Corrosion Studies of Candidate Materials for European HPLWR

    AU - Penttilä, Sami

    AU - Toivonen, Aki

    AU - Heikinheimo, Liisa

    AU - Novotny, Radek

    N1 - Project code: 20062

    PY - 2010

    Y1 - 2010

    N2 - The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; however, the material requirements for HPLWR offer challenges because of the extreme operating temperatures and pressures. Consequently, general corrosion rates were studied in water at 300 to 650°C at supercritical pressure using weight gain measurements. Oxide thicknesses were determined from cross-section samples. The compositions of the oxide layers were analyzed using scanning electron microscopy in conjuction with energy dispersive spectroscopy. The surface layers of selected samples were analyzed also by X-ray diffraction. The test matrix included ten materials from four alloy classes: ferritic/martensitic steels, oxide dispersion strengthened (ODS) steels, austenitic stainless steels, and nickel-base alloys. A high oxidation resistance was seen in Ni-base alloy 625, austenitic stainless steels with high Cr content (>18 wt% Cr), and an ODS steel containing 20% Cr at all applied test temperatures (300 to 650°C). The oxidation rates of austenitic stainless steels with lower Cr content, 15 to 18%, increase considerably at temperatures >500°C. The oxidation rates of 9% Cr ODS steels were moderate or high at all temperatures. Ferritic/martensitic steels showed high oxidation rates at all temperatures.

    AB - The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; however, the material requirements for HPLWR offer challenges because of the extreme operating temperatures and pressures. Consequently, general corrosion rates were studied in water at 300 to 650°C at supercritical pressure using weight gain measurements. Oxide thicknesses were determined from cross-section samples. The compositions of the oxide layers were analyzed using scanning electron microscopy in conjuction with energy dispersive spectroscopy. The surface layers of selected samples were analyzed also by X-ray diffraction. The test matrix included ten materials from four alloy classes: ferritic/martensitic steels, oxide dispersion strengthened (ODS) steels, austenitic stainless steels, and nickel-base alloys. A high oxidation resistance was seen in Ni-base alloy 625, austenitic stainless steels with high Cr content (>18 wt% Cr), and an ODS steel containing 20% Cr at all applied test temperatures (300 to 650°C). The oxidation rates of austenitic stainless steels with lower Cr content, 15 to 18%, increase considerably at temperatures >500°C. The oxidation rates of 9% Cr ODS steels were moderate or high at all temperatures. Ferritic/martensitic steels showed high oxidation rates at all temperatures.

    KW - SCWR

    KW - general corrosion

    KW - candidate alloys

    U2 - 10.13182/NT10-A9463

    DO - 10.13182/NT10-A9463

    M3 - Article

    VL - 170

    SP - 261

    EP - 271

    JO - Nuclear Technology

    JF - Nuclear Technology

    SN - 0029-5450

    IS - 1

    ER -