Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy: COFAT 2

Bachu Narain Singh, Bjorn Sejr Johansen, Seppo Tähtinen, Pekka Moilanen, S. Saarela, P. Jacquet, J. Dekeyser, J.F. Stubbins

    Research output: Book/ReportReport

    Abstract

    The main objective of the present work was to determine experimentally the mechanical response and resulting microstructural changes in CuCrZr (HT1) alloy exposed concurrently to flux of neutrons and creep-fatigue cyclic loading directly in a fission reactor. Using specially designed test facilities for this purpose, in-reactor creep-fatigue tests have been performed at strain amplitudes of 0.25 and 0.35 % with a holdtime of 10s in the BR-2 reactor at Mol (Belgium). These tests were performed at the ambient temperatures of 326K and 323K. For comparison purposes corresponding out-of-reactor creep-fatigue tests were also carried out. In the following we first describe the details of the creep-fatigue experiments. We then present the main results on the mechanical response of the material in the form of hysteresis loops and the maximum stress amplitude as a function of the number of creep-fatigue cycles during the out-of-reactor and the in-reactor tests carried out at different strain amplitudes. Finally, the dependence of the number of cycles to failure (i.e. creep-fatigue lifetime) on the strain amplitudes is shown. The details of microstructure of the specimens tested out-of-reactor as well as in the reactor were investigated using transmission electron microscopy. The main results on the mechanical response as well as changes in the microstructure are briefly discussed. The main conclusion emerging from the present work is that the lifetime of the in-reactor tested specimens is by a factor of about two longer than in the case of corresponding out-of-reactor tests.
    Original languageEnglish
    Place of PublicationRoskilde, DK
    Number of pages41
    Publication statusPublished - 2008
    MoE publication typeD4 Published development or research report or study

    Publication series

    SeriesRisø-R
    Number1629(EN)
    ISSN0106-2840

    Fingerprint

    reactors
    fatigue tests
    Belgium
    life (durability)
    microstructure
    cycles
    test facilities
    ambient temperature
    fission
    emerging
    hysteresis
    neutrons
    transmission electron microscopy

    Cite this

    Singh, B. N., Johansen, B. S., Tähtinen, S., Moilanen, P., Saarela, S., Jacquet, P., ... Stubbins, J. F. (2008). Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy: COFAT 2. Roskilde, DK. Risø-R, No. 1629(EN)
    Singh, Bachu Narain ; Johansen, Bjorn Sejr ; Tähtinen, Seppo ; Moilanen, Pekka ; Saarela, S. ; Jacquet, P. ; Dekeyser, J. ; Stubbins, J.F. / Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy : COFAT 2. Roskilde, DK, 2008. 41 p. (Risø-R; No. 1629(EN)).
    @book{518de7566aa04b5e8227cd01b7135413,
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    abstract = "The main objective of the present work was to determine experimentally the mechanical response and resulting microstructural changes in CuCrZr (HT1) alloy exposed concurrently to flux of neutrons and creep-fatigue cyclic loading directly in a fission reactor. Using specially designed test facilities for this purpose, in-reactor creep-fatigue tests have been performed at strain amplitudes of 0.25 and 0.35 {\%} with a holdtime of 10s in the BR-2 reactor at Mol (Belgium). These tests were performed at the ambient temperatures of 326K and 323K. For comparison purposes corresponding out-of-reactor creep-fatigue tests were also carried out. In the following we first describe the details of the creep-fatigue experiments. We then present the main results on the mechanical response of the material in the form of hysteresis loops and the maximum stress amplitude as a function of the number of creep-fatigue cycles during the out-of-reactor and the in-reactor tests carried out at different strain amplitudes. Finally, the dependence of the number of cycles to failure (i.e. creep-fatigue lifetime) on the strain amplitudes is shown. The details of microstructure of the specimens tested out-of-reactor as well as in the reactor were investigated using transmission electron microscopy. The main results on the mechanical response as well as changes in the microstructure are briefly discussed. The main conclusion emerging from the present work is that the lifetime of the in-reactor tested specimens is by a factor of about two longer than in the case of corresponding out-of-reactor tests.",
    author = "Singh, {Bachu Narain} and Johansen, {Bjorn Sejr} and Seppo T{\"a}htinen and Pekka Moilanen and S. Saarela and P. Jacquet and J. Dekeyser and J.F. Stubbins",
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    Singh, BN, Johansen, BS, Tähtinen, S, Moilanen, P, Saarela, S, Jacquet, P, Dekeyser, J & Stubbins, JF 2008, Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy: COFAT 2. Risø-R, no. 1629(EN), Roskilde, DK.

    Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy : COFAT 2. / Singh, Bachu Narain; Johansen, Bjorn Sejr; Tähtinen, Seppo; Moilanen, Pekka; Saarela, S.; Jacquet, P.; Dekeyser, J.; Stubbins, J.F.

    Roskilde, DK, 2008. 41 p. (Risø-R; No. 1629(EN)).

    Research output: Book/ReportReport

    TY - BOOK

    T1 - Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy

    T2 - COFAT 2

    AU - Singh, Bachu Narain

    AU - Johansen, Bjorn Sejr

    AU - Tähtinen, Seppo

    AU - Moilanen, Pekka

    AU - Saarela, S.

    AU - Jacquet, P.

    AU - Dekeyser, J.

    AU - Stubbins, J.F.

    PY - 2008

    Y1 - 2008

    N2 - The main objective of the present work was to determine experimentally the mechanical response and resulting microstructural changes in CuCrZr (HT1) alloy exposed concurrently to flux of neutrons and creep-fatigue cyclic loading directly in a fission reactor. Using specially designed test facilities for this purpose, in-reactor creep-fatigue tests have been performed at strain amplitudes of 0.25 and 0.35 % with a holdtime of 10s in the BR-2 reactor at Mol (Belgium). These tests were performed at the ambient temperatures of 326K and 323K. For comparison purposes corresponding out-of-reactor creep-fatigue tests were also carried out. In the following we first describe the details of the creep-fatigue experiments. We then present the main results on the mechanical response of the material in the form of hysteresis loops and the maximum stress amplitude as a function of the number of creep-fatigue cycles during the out-of-reactor and the in-reactor tests carried out at different strain amplitudes. Finally, the dependence of the number of cycles to failure (i.e. creep-fatigue lifetime) on the strain amplitudes is shown. The details of microstructure of the specimens tested out-of-reactor as well as in the reactor were investigated using transmission electron microscopy. The main results on the mechanical response as well as changes in the microstructure are briefly discussed. The main conclusion emerging from the present work is that the lifetime of the in-reactor tested specimens is by a factor of about two longer than in the case of corresponding out-of-reactor tests.

    AB - The main objective of the present work was to determine experimentally the mechanical response and resulting microstructural changes in CuCrZr (HT1) alloy exposed concurrently to flux of neutrons and creep-fatigue cyclic loading directly in a fission reactor. Using specially designed test facilities for this purpose, in-reactor creep-fatigue tests have been performed at strain amplitudes of 0.25 and 0.35 % with a holdtime of 10s in the BR-2 reactor at Mol (Belgium). These tests were performed at the ambient temperatures of 326K and 323K. For comparison purposes corresponding out-of-reactor creep-fatigue tests were also carried out. In the following we first describe the details of the creep-fatigue experiments. We then present the main results on the mechanical response of the material in the form of hysteresis loops and the maximum stress amplitude as a function of the number of creep-fatigue cycles during the out-of-reactor and the in-reactor tests carried out at different strain amplitudes. Finally, the dependence of the number of cycles to failure (i.e. creep-fatigue lifetime) on the strain amplitudes is shown. The details of microstructure of the specimens tested out-of-reactor as well as in the reactor were investigated using transmission electron microscopy. The main results on the mechanical response as well as changes in the microstructure are briefly discussed. The main conclusion emerging from the present work is that the lifetime of the in-reactor tested specimens is by a factor of about two longer than in the case of corresponding out-of-reactor tests.

    M3 - Report

    SN - 978-87-550-3651-2

    T3 - Risø-R

    BT - Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy

    CY - Roskilde, DK

    ER -

    Singh BN, Johansen BS, Tähtinen S, Moilanen P, Saarela S, Jacquet P et al. Final report on in-reactor creep-fatigue deformation behaviour of a CuCrZr alloy: COFAT 2. Roskilde, DK, 2008. 41 p. (Risø-R; No. 1629(EN)).