Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock

Horst Kordisch, Heli Talja, Gunter Neubrech

    Research output: Contribution to journalArticleScientificpeer-review

    6 Citations (Scopus)

    Abstract

    In order to simulate a nuclear emergency cooling situation, longterm cooling tests (pressurized thermal shocks) were carried out under normal operating conditions on the reactor pressure vessel of the HDR (hot steam reactor). Naturally occuring circumferential cracks in the cylindrical part of the RPV, previously induced during cyclic thermal shock tests, were subjected to internal pressure and thermal stresses.
    The aim of the test was crack initiation and a limited amount of stable crack growth.

    Analyses, applying fracture mechanical assessment methods, were carried out before and after the test and these checked against the experimental results. To this end, comprehensive numerical analyses, investigations into material property characteristics, non-destructive and destructive (fractographical) tests were carried out. Due to the conservative assumptions, the results of the precalculation lay on the safe side; this was intended as these results served, among other aspects, as the basis for the experimental boundary condition.
    The post calculation which was based on the actual crack geometry, the measured cooling medium temperature and the material properties local to the crack, was in good agreement with the experimental results.
    Thus a tool is now available which can be successfully applied to the assessment of cracks in reactor components.
    Original languageEnglish
    Pages (from-to)171-192
    JournalNuclear Engineering and Design
    Volume124
    Issue number1-2
    DOIs
    Publication statusPublished - 1990
    MoE publication typeA1 Journal article-refereed

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    remotely piloted vehicles
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    crack
    cracks
    Cracks
    reactors
    Cooling
    cooling
    Materials properties
    destructive tests
    crack geometry
    shock tests
    pressure vessels
    internal pressure
    crack initiation
    emergencies
    Steam
    thermal stresses
    Pressure vessels

    Cite this

    Kordisch, Horst ; Talja, Heli ; Neubrech, Gunter. / Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock. In: Nuclear Engineering and Design. 1990 ; Vol. 124, No. 1-2. pp. 171-192.
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    title = "Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock",
    abstract = "In order to simulate a nuclear emergency cooling situation, longterm cooling tests (pressurized thermal shocks) were carried out under normal operating conditions on the reactor pressure vessel of the HDR (hot steam reactor). Naturally occuring circumferential cracks in the cylindrical part of the RPV, previously induced during cyclic thermal shock tests, were subjected to internal pressure and thermal stresses. The aim of the test was crack initiation and a limited amount of stable crack growth.Analyses, applying fracture mechanical assessment methods, were carried out before and after the test and these checked against the experimental results. To this end, comprehensive numerical analyses, investigations into material property characteristics, non-destructive and destructive (fractographical) tests were carried out. Due to the conservative assumptions, the results of the precalculation lay on the safe side; this was intended as these results served, among other aspects, as the basis for the experimental boundary condition. The post calculation which was based on the actual crack geometry, the measured cooling medium temperature and the material properties local to the crack, was in good agreement with the experimental results. Thus a tool is now available which can be successfully applied to the assessment of cracks in reactor components.",
    author = "Horst Kordisch and Heli Talja and Gunter Neubrech",
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    Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock. / Kordisch, Horst; Talja, Heli; Neubrech, Gunter.

    In: Nuclear Engineering and Design, Vol. 124, No. 1-2, 1990, p. 171-192.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Analysis of initation and growth of a circumferential crack in the HDR-RPV-cylinder under pressurized thermal shock

    AU - Kordisch, Horst

    AU - Talja, Heli

    AU - Neubrech, Gunter

    PY - 1990

    Y1 - 1990

    N2 - In order to simulate a nuclear emergency cooling situation, longterm cooling tests (pressurized thermal shocks) were carried out under normal operating conditions on the reactor pressure vessel of the HDR (hot steam reactor). Naturally occuring circumferential cracks in the cylindrical part of the RPV, previously induced during cyclic thermal shock tests, were subjected to internal pressure and thermal stresses. The aim of the test was crack initiation and a limited amount of stable crack growth.Analyses, applying fracture mechanical assessment methods, were carried out before and after the test and these checked against the experimental results. To this end, comprehensive numerical analyses, investigations into material property characteristics, non-destructive and destructive (fractographical) tests were carried out. Due to the conservative assumptions, the results of the precalculation lay on the safe side; this was intended as these results served, among other aspects, as the basis for the experimental boundary condition. The post calculation which was based on the actual crack geometry, the measured cooling medium temperature and the material properties local to the crack, was in good agreement with the experimental results. Thus a tool is now available which can be successfully applied to the assessment of cracks in reactor components.

    AB - In order to simulate a nuclear emergency cooling situation, longterm cooling tests (pressurized thermal shocks) were carried out under normal operating conditions on the reactor pressure vessel of the HDR (hot steam reactor). Naturally occuring circumferential cracks in the cylindrical part of the RPV, previously induced during cyclic thermal shock tests, were subjected to internal pressure and thermal stresses. The aim of the test was crack initiation and a limited amount of stable crack growth.Analyses, applying fracture mechanical assessment methods, were carried out before and after the test and these checked against the experimental results. To this end, comprehensive numerical analyses, investigations into material property characteristics, non-destructive and destructive (fractographical) tests were carried out. Due to the conservative assumptions, the results of the precalculation lay on the safe side; this was intended as these results served, among other aspects, as the basis for the experimental boundary condition. The post calculation which was based on the actual crack geometry, the measured cooling medium temperature and the material properties local to the crack, was in good agreement with the experimental results. Thus a tool is now available which can be successfully applied to the assessment of cracks in reactor components.

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    DO - 10.1016/0029-5493(90)90363-3

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    JF - Nuclear Engineering and Design

    SN - 0029-5493

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