In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC

B.N. Singh (Corresponding Author), Seppo Tähtinen, P. Moilanen, P. Jacquet, J. Dekeyser

    Research output: Contribution to journalArticleScientificpeer-review

    12 Citations (Scopus)

    Abstract

    Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress response was continuously recorded as a function of irradiation time (i.e. displacement dose and strain). The experiment lasted for 308 h. During the dynamic in-reactor test, the specimen deformed and hardened homogeneously without showing any sign of yield drop and plastic instability. However, the specimen yielded a uniform elongation of only about 12%. The preliminary results are briefly described and discussed in the present note.
    Original languageEnglish
    Pages (from-to)299-304
    Number of pages6
    JournalJournal of Nuclear Materials
    Volume320
    Issue number3
    DOIs
    Publication statusPublished - 2003
    MoE publication typeA1 Journal article-refereed

    Fingerprint

    Tensile testing
    Nuclear reactors
    Dosimetry
    strain rate
    Strain rate
    Copper
    Elongation
    reactors
    Irradiation
    Plastics
    copper
    Experiments
    Temperature
    elongation
    fission
    plastics
    damage
    dosage
    irradiation
    temperature

    Keywords

    • irradiation
    • irradiation damage
    • irradiation embrittlement
    • neutron irradiation
    • deformation

    Cite this

    Singh, B.N. ; Tähtinen, Seppo ; Moilanen, P. ; Jacquet, P. ; Dekeyser, J. / In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC. In: Journal of Nuclear Materials. 2003 ; Vol. 320, No. 3. pp. 299-304.
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    abstract = "Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress response was continuously recorded as a function of irradiation time (i.e. displacement dose and strain). The experiment lasted for 308 h. During the dynamic in-reactor test, the specimen deformed and hardened homogeneously without showing any sign of yield drop and plastic instability. However, the specimen yielded a uniform elongation of only about 12{\%}. The preliminary results are briefly described and discussed in the present note.",
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    author = "B.N. Singh and Seppo T{\"a}htinen and P. Moilanen and P. Jacquet and J. Dekeyser",
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    In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC. / Singh, B.N. (Corresponding Author); Tähtinen, Seppo; Moilanen, P.; Jacquet, P.; Dekeyser, J.

    In: Journal of Nuclear Materials, Vol. 320, No. 3, 2003, p. 299-304.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC

    AU - Singh, B.N.

    AU - Tähtinen, Seppo

    AU - Moilanen, P.

    AU - Jacquet, P.

    AU - Dekeyser, J.

    PY - 2003

    Y1 - 2003

    N2 - Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress response was continuously recorded as a function of irradiation time (i.e. displacement dose and strain). The experiment lasted for 308 h. During the dynamic in-reactor test, the specimen deformed and hardened homogeneously without showing any sign of yield drop and plastic instability. However, the specimen yielded a uniform elongation of only about 12%. The preliminary results are briefly described and discussed in the present note.

    AB - Recently, annealed specimens of pure copper have been tensile tested in a fission reactor at a damage rate of 6 × 10−8 dpa/s with a constant strain rate of 1.3 × 10−7 s−1. The specimen temperature during the test was about 90 °C. The stress response was continuously recorded as a function of irradiation time (i.e. displacement dose and strain). The experiment lasted for 308 h. During the dynamic in-reactor test, the specimen deformed and hardened homogeneously without showing any sign of yield drop and plastic instability. However, the specimen yielded a uniform elongation of only about 12%. The preliminary results are briefly described and discussed in the present note.

    KW - irradiation

    KW - irradiation damage

    KW - irradiation embrittlement

    KW - neutron irradiation

    KW - deformation

    U2 - 10.1016/S0022-3115(03)00234-4

    DO - 10.1016/S0022-3115(03)00234-4

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    VL - 320

    SP - 299

    EP - 304

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    IS - 3

    ER -