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

    15 Citations (Scopus)


    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
    Issue number3
    Publication statusPublished - 2003
    MoE publication typeA1 Journal article-refereed


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


    Dive into the research topics of 'In-reactor uniaxial tensile testing of pure copper at a constant strain rate at 90 ºC'. Together they form a unique fingerprint.

    Cite this