Corrosion and creep studies of candidate in-core materials for Generation IV supercritical water reactor

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientific

    Abstract

    The High Performance Light Water Reactor (HPLWR) design is one of the concepts chosen for Generation IV reactors; HPLWR uses supercritical water as coolant with design reactor outlet temperature at about 500 °C. The out-of-core material choices can be conveniently adopted e.g. from conventional coal-fired supercritical power plants. However, in the core area radiation sets additional requirements for the construction materials. In addition to resistance to stress corrosion cracking, also oxidation resistance and creep resistance become important. The materials currently under study for application in the HPLWR in-core area can be divided into four categories: ferritic/martensitic steels, oxide dispersion strengthened (ODS) steels, austenitic stainless steels, and nickel-base alloys. This paper discusses the resistance to oxidation, creep and stress corrosion cracking of selected sets of these materials in the temperature range 300 to 650 °C. Based on the material studies done the present candidate materials for the core internals of the European SCWR are austenitic stainless steels, which have a good enough oxidation and creep resistance up to 500 °C or even 550 °C. High chromium austenitic steels and ferritic/martensitic ODS steels are considered, in long term, for the fuel rod cladding because of their good oxidation resistance up to 650 °C.
    Original languageEnglish
    Title of host publicationProceedings of the 2nd international conference on advances in nuclear materials
    Subtitle of host publicationAbstract booklet and souvenir
    Place of PublicationMumbai
    PublisherBhabha Atomic Research Centre (BARC)
    Publication statusPublished - 2011
    MoE publication typeB3 Non-refereed article in conference proceedings
    Event2nd International Conference on Advances in Nuclear Materials, ANM 2011 - Mumbai, India
    Duration: 9 Feb 201111 Feb 2011

    Conference

    Conference2nd International Conference on Advances in Nuclear Materials, ANM 2011
    Abbreviated titleANM 2011
    CountryIndia
    CityMumbai
    Period9/02/1111/02/11

    Keywords

    • GenIV
    • supercritical water
    • corrosion
    • stress corrosion cracking
    • creep

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