Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel

Heikki Keinänen, Heli Talja, Rauno Rintamaa, Kari Törrönen, Ralf Ahlstrand, Pekka Nurkkala, Georgy Karzov, Boris Timofeev, Alexander Blumin

    Research output: Contribution to journalArticleScientificpeer-review

    3 Citations (Scopus)

    Abstract

    A joint pressure vessel integrity research programme involving three partners is being carried out during 1990–1995. The partners are the Central Research Institute of Structural Materials “Prometey” from Russia, IVO International Ltd (IVO) from Finland, and the Technical Research Centre of Finland (VTT). The main objective of the research programme is to increase the reliability of the VVER-440 reactor pressure vessel safety analysis. This is achieved by providing material property data for the VVER-440 pressure vessel steel, and by producing experimental understanding of the crack behaviour in pressurized thermal shock loading for the validation of different fracture assessment methods.
    The programme is divided into four parts: pressure vessel tests, material characterization, computational fracture analyses, and evaluation of the analysis methods. The testing programme comprises tests on two model pressure vessels with artificial axial outer surface flaws. The first model vessel had circumferential weld seam at the mid-length of the vessel. A special embrittling heat treatment is applied to the vessels before tests to simulate the fracture toughness at the end-of-life condition of a real reactor pressure vessel.
    The sixth test on the first model led to crack initiation followed by arrest. After the testing phase, material characterization was performed.
    Comparison of calculated and experimental data generally led to a good correlation, although the work is being continued to resolve the discrepancies between the measured initiation and arrest properties of the material.

    Original languageEnglish
    Pages (from-to)217-226
    JournalNuclear Engineering and Design
    Volume158
    Issue number2-3
    DOIs
    Publication statusPublished - 1995
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    crack arrest
    shock tests
    pressure vessels
    thermal shock
    crack initiation
    Thermal shock
    Steel structures
    Pressure vessels
    Crack initiation
    crack
    vessel
    steel
    reactors
    steels
    vessels
    Finland
    Testing
    materials tests
    research program
    Fracture toughness

    Cite this

    Keinänen, Heikki ; Talja, Heli ; Rintamaa, Rauno ; Törrönen, Kari ; Ahlstrand, Ralf ; Nurkkala, Pekka ; Karzov, Georgy ; Timofeev, Boris ; Blumin, Alexander. / Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel. In: Nuclear Engineering and Design. 1995 ; Vol. 158, No. 2-3. pp. 217-226.
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    title = "Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel",
    abstract = "A joint pressure vessel integrity research programme involving three partners is being carried out during 1990–1995. The partners are the Central Research Institute of Structural Materials “Prometey” from Russia, IVO International Ltd (IVO) from Finland, and the Technical Research Centre of Finland (VTT). The main objective of the research programme is to increase the reliability of the VVER-440 reactor pressure vessel safety analysis. This is achieved by providing material property data for the VVER-440 pressure vessel steel, and by producing experimental understanding of the crack behaviour in pressurized thermal shock loading for the validation of different fracture assessment methods. The programme is divided into four parts: pressure vessel tests, material characterization, computational fracture analyses, and evaluation of the analysis methods. The testing programme comprises tests on two model pressure vessels with artificial axial outer surface flaws. The first model vessel had circumferential weld seam at the mid-length of the vessel. A special embrittling heat treatment is applied to the vessels before tests to simulate the fracture toughness at the end-of-life condition of a real reactor pressure vessel. The sixth test on the first model led to crack initiation followed by arrest. After the testing phase, material characterization was performed. Comparison of calculated and experimental data generally led to a good correlation, although the work is being continued to resolve the discrepancies between the measured initiation and arrest properties of the material.",
    author = "Heikki Kein{\"a}nen and Heli Talja and Rauno Rintamaa and Kari T{\"o}rr{\"o}nen and Ralf Ahlstrand and Pekka Nurkkala and Georgy Karzov and Boris Timofeev and Alexander Blumin",
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    Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel. / Keinänen, Heikki; Talja, Heli; Rintamaa, Rauno; Törrönen, Kari; Ahlstrand, Ralf; Nurkkala, Pekka; Karzov, Georgy; Timofeev, Boris; Blumin, Alexander.

    In: Nuclear Engineering and Design, Vol. 158, No. 2-3, 1995, p. 217-226.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Crack initiation and arrest in a pressurized thermal shock test for a model pressure vessel made of VVER-440 reactor pressure vessel steel

    AU - Keinänen, Heikki

    AU - Talja, Heli

    AU - Rintamaa, Rauno

    AU - Törrönen, Kari

    AU - Ahlstrand, Ralf

    AU - Nurkkala, Pekka

    AU - Karzov, Georgy

    AU - Timofeev, Boris

    AU - Blumin, Alexander

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    PY - 1995

    Y1 - 1995

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    AB - A joint pressure vessel integrity research programme involving three partners is being carried out during 1990–1995. The partners are the Central Research Institute of Structural Materials “Prometey” from Russia, IVO International Ltd (IVO) from Finland, and the Technical Research Centre of Finland (VTT). The main objective of the research programme is to increase the reliability of the VVER-440 reactor pressure vessel safety analysis. This is achieved by providing material property data for the VVER-440 pressure vessel steel, and by producing experimental understanding of the crack behaviour in pressurized thermal shock loading for the validation of different fracture assessment methods. The programme is divided into four parts: pressure vessel tests, material characterization, computational fracture analyses, and evaluation of the analysis methods. The testing programme comprises tests on two model pressure vessels with artificial axial outer surface flaws. The first model vessel had circumferential weld seam at the mid-length of the vessel. A special embrittling heat treatment is applied to the vessels before tests to simulate the fracture toughness at the end-of-life condition of a real reactor pressure vessel. The sixth test on the first model led to crack initiation followed by arrest. After the testing phase, material characterization was performed. Comparison of calculated and experimental data generally led to a good correlation, although the work is being continued to resolve the discrepancies between the measured initiation and arrest properties of the material.

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    DO - 10.1016/0029-5493(95)01030-L

    M3 - Article

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    JO - Nuclear Engineering and Design

    JF - Nuclear Engineering and Design

    SN - 0029-5493

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    ER -