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

  • B.N. Singh*
  • , Seppo Tähtinen
  • , P. Moilanen
  • , P. Jacquet
  • , J. Dekeyser
  • *Corresponding author for this work
    • Risø DTU National Laboratory for Sustainable Energy
    • Belgian Nuclear Research Centre (SCK CEN)

    Research output: Contribution to journalArticleScientificpeer-review

    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
    JournalJournal of Nuclear Materials
    Volume320
    Issue number3
    DOIs
    Publication statusPublished - 2003
    MoE publication typeA1 Journal article-refereed

    Keywords

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

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