Pre-test analyses for pressurized thermoshock tests. Vessel I

Heli Talja, Heikki Keinänen

    Research output: Book/ReportReport

    Abstract

    This report describes the pre-test analyses performed for the thermoshock tests with the first model pressure vessel conducted at the Prometey Institute in Gatsina, U.S.S.R.. The calculations were performed at the Nuclear Engineering Laboratory and at the Metals Laboratory of the Technical Research Centre of Finland. Mainly simplified calculation methods were used in the pre-test analyses. The temperature calculation was made using both a computer code based on the Fourier series and the finite-element method. As the next step the stresses due to internal pressure and thermal transient were calculated using both analytical formulas and the finite-element method. To evaluate the structural integrity, the VTTSIF program based on the influence function method was applied to obtain the stress intensity factor values, which were compared to material toughness values obtained from the Prometey Institute. So far, five tests have been made with the same model pressure vessel using four different flaw geometries. In the first three tests, the flaw was actually a blunt notch. In the last two tests (tests 4 and 5), a sharp pre-crack was produced before the test. Test 6, which is considered as the final test, will be performed using the same flaw as in test 5. The calculated temperatures and stresses are presented in this report. When these are compared to measured values, a good correlation is observed. For each flaw the assessment is performed and for the last flaw geometry (test 6) the calculated stress intensity is presented as a function of loading time and crack tip temperature. When this stress intensity factor is compared to the material fracture initiation toughness values obtained from the Prometey Institute, crack initiation is clearly predicted.
    Original languageEnglish
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Number of pages42
    ISBN (Print)951-38-3994-X
    Publication statusPublished - 1991
    MoE publication typeD4 Published development or research report or study

    Publication series

    SeriesValtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports
    Number746
    ISSN0358-5077

    Fingerprint

    Defects
    Pressure vessels
    Stress intensity factors
    Toughness
    Nuclear engineering
    Finite element method
    Geometry
    Fourier series
    Structural integrity
    Crack initiation
    Crack tips
    Temperature
    Cracks
    Metals

    Keywords

    • nuclear reactors
    • pressure vessels
    • testing
    • thermal shock
    • materials testing
    • properties

    Cite this

    Talja, H., & Keinänen, H. (1991). Pre-test analyses for pressurized thermoshock tests. Vessel I. Espoo: VTT Technical Research Centre of Finland. Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports, No. 746
    Talja, Heli ; Keinänen, Heikki. / Pre-test analyses for pressurized thermoshock tests. Vessel I. Espoo : VTT Technical Research Centre of Finland, 1991. 42 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 746).
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    Talja, H & Keinänen, H 1991, Pre-test analyses for pressurized thermoshock tests. Vessel I. Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports, no. 746, VTT Technical Research Centre of Finland, Espoo.

    Pre-test analyses for pressurized thermoshock tests. Vessel I. / Talja, Heli; Keinänen, Heikki.

    Espoo : VTT Technical Research Centre of Finland, 1991. 42 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 746).

    Research output: Book/ReportReport

    TY - BOOK

    T1 - Pre-test analyses for pressurized thermoshock tests. Vessel I

    AU - Talja, Heli

    AU - Keinänen, Heikki

    PY - 1991

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    N2 - This report describes the pre-test analyses performed for the thermoshock tests with the first model pressure vessel conducted at the Prometey Institute in Gatsina, U.S.S.R.. The calculations were performed at the Nuclear Engineering Laboratory and at the Metals Laboratory of the Technical Research Centre of Finland. Mainly simplified calculation methods were used in the pre-test analyses. The temperature calculation was made using both a computer code based on the Fourier series and the finite-element method. As the next step the stresses due to internal pressure and thermal transient were calculated using both analytical formulas and the finite-element method. To evaluate the structural integrity, the VTTSIF program based on the influence function method was applied to obtain the stress intensity factor values, which were compared to material toughness values obtained from the Prometey Institute. So far, five tests have been made with the same model pressure vessel using four different flaw geometries. In the first three tests, the flaw was actually a blunt notch. In the last two tests (tests 4 and 5), a sharp pre-crack was produced before the test. Test 6, which is considered as the final test, will be performed using the same flaw as in test 5. The calculated temperatures and stresses are presented in this report. When these are compared to measured values, a good correlation is observed. For each flaw the assessment is performed and for the last flaw geometry (test 6) the calculated stress intensity is presented as a function of loading time and crack tip temperature. When this stress intensity factor is compared to the material fracture initiation toughness values obtained from the Prometey Institute, crack initiation is clearly predicted.

    AB - This report describes the pre-test analyses performed for the thermoshock tests with the first model pressure vessel conducted at the Prometey Institute in Gatsina, U.S.S.R.. The calculations were performed at the Nuclear Engineering Laboratory and at the Metals Laboratory of the Technical Research Centre of Finland. Mainly simplified calculation methods were used in the pre-test analyses. The temperature calculation was made using both a computer code based on the Fourier series and the finite-element method. As the next step the stresses due to internal pressure and thermal transient were calculated using both analytical formulas and the finite-element method. To evaluate the structural integrity, the VTTSIF program based on the influence function method was applied to obtain the stress intensity factor values, which were compared to material toughness values obtained from the Prometey Institute. So far, five tests have been made with the same model pressure vessel using four different flaw geometries. In the first three tests, the flaw was actually a blunt notch. In the last two tests (tests 4 and 5), a sharp pre-crack was produced before the test. Test 6, which is considered as the final test, will be performed using the same flaw as in test 5. The calculated temperatures and stresses are presented in this report. When these are compared to measured values, a good correlation is observed. For each flaw the assessment is performed and for the last flaw geometry (test 6) the calculated stress intensity is presented as a function of loading time and crack tip temperature. When this stress intensity factor is compared to the material fracture initiation toughness values obtained from the Prometey Institute, crack initiation is clearly predicted.

    KW - nuclear reactors

    KW - pressure vessels

    KW - testing

    KW - thermal shock

    KW - materials testing

    KW - properties

    M3 - Report

    SN - 951-38-3994-X

    T3 - Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports

    BT - Pre-test analyses for pressurized thermoshock tests. Vessel I

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Talja H, Keinänen H. Pre-test analyses for pressurized thermoshock tests. Vessel I. Espoo: VTT Technical Research Centre of Finland, 1991. 42 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 746).