A comparative TEM study of in-reactor and post-irradiation tensile tested copper

Janne Pakarinen (Corresponding Author), Seppo Tähtinen, B.N. Singh

    Research output: Contribution to journalArticleScientificpeer-review

    1 Citation (Scopus)

    Abstract

    The deformation microstructures of oxygen-free high-conductivity (OFHC) copper were examined by transmission electron microscopy (TEM) following in-reactor and post-irradiation slow strain rate tensile tests. The TEM results suggest that the main modes of deformation differ between all examined cases. Plastic deformation appeared predominantly localized in the defect-free cleared channels following post-irradiation testing and hardly any dislocations were seen outside the channels. The microstructures following in-reactor tests were characterized by a small amount of cleared channels and a distinct dislocation density within the matrix. However, the dislocations observed following in-reactor testing did not seem to interact with each other, whereas that was the main mode of deformation in the non-irradiated reference sample. The possible mechanisms of plastic deformation are discussed based on the experimental results
    Original languageEnglish
    Pages (from-to)S821-S825
    JournalJournal of Nuclear Materials
    Volume442
    Issue number1-3 suppl.1
    DOIs
    Publication statusPublished - 2013
    MoE publication typeA1 Journal article-refereed
    EventFifteenth International Conference on Fusion Reactor Materials - Charleston, United States
    Duration: 16 Oct 201122 Oct 2011

    Fingerprint

    Copper
    reactors
    Irradiation
    Transmission electron microscopy
    copper
    transmission electron microscopy
    plastic deformation
    irradiation
    Plastic deformation
    microstructure
    Microstructure
    Testing
    tensile tests
    strain rate
    Strain rate
    Oxygen
    conductivity
    Defects
    defects
    oxygen

    Cite this

    Pakarinen, Janne ; Tähtinen, Seppo ; Singh, B.N. / A comparative TEM study of in-reactor and post-irradiation tensile tested copper. In: Journal of Nuclear Materials. 2013 ; Vol. 442, No. 1-3 suppl.1. pp. S821-S825.
    @article{d2dca00cf5754e6a8a0f71d1c681c141,
    title = "A comparative TEM study of in-reactor and post-irradiation tensile tested copper",
    abstract = "The deformation microstructures of oxygen-free high-conductivity (OFHC) copper were examined by transmission electron microscopy (TEM) following in-reactor and post-irradiation slow strain rate tensile tests. The TEM results suggest that the main modes of deformation differ between all examined cases. Plastic deformation appeared predominantly localized in the defect-free cleared channels following post-irradiation testing and hardly any dislocations were seen outside the channels. The microstructures following in-reactor tests were characterized by a small amount of cleared channels and a distinct dislocation density within the matrix. However, the dislocations observed following in-reactor testing did not seem to interact with each other, whereas that was the main mode of deformation in the non-irradiated reference sample. The possible mechanisms of plastic deformation are discussed based on the experimental results",
    author = "Janne Pakarinen and Seppo T{\"a}htinen and B.N. Singh",
    year = "2013",
    doi = "10.1016/j.jnucmat.2012.10.014",
    language = "English",
    volume = "442",
    pages = "S821--S825",
    journal = "Journal of Nuclear Materials",
    issn = "0022-3115",
    publisher = "Elsevier",
    number = "1-3 suppl.1",

    }

    A comparative TEM study of in-reactor and post-irradiation tensile tested copper. / Pakarinen, Janne (Corresponding Author); Tähtinen, Seppo; Singh, B.N.

    In: Journal of Nuclear Materials, Vol. 442, No. 1-3 suppl.1, 2013, p. S821-S825.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - A comparative TEM study of in-reactor and post-irradiation tensile tested copper

    AU - Pakarinen, Janne

    AU - Tähtinen, Seppo

    AU - Singh, B.N.

    PY - 2013

    Y1 - 2013

    N2 - The deformation microstructures of oxygen-free high-conductivity (OFHC) copper were examined by transmission electron microscopy (TEM) following in-reactor and post-irradiation slow strain rate tensile tests. The TEM results suggest that the main modes of deformation differ between all examined cases. Plastic deformation appeared predominantly localized in the defect-free cleared channels following post-irradiation testing and hardly any dislocations were seen outside the channels. The microstructures following in-reactor tests were characterized by a small amount of cleared channels and a distinct dislocation density within the matrix. However, the dislocations observed following in-reactor testing did not seem to interact with each other, whereas that was the main mode of deformation in the non-irradiated reference sample. The possible mechanisms of plastic deformation are discussed based on the experimental results

    AB - The deformation microstructures of oxygen-free high-conductivity (OFHC) copper were examined by transmission electron microscopy (TEM) following in-reactor and post-irradiation slow strain rate tensile tests. The TEM results suggest that the main modes of deformation differ between all examined cases. Plastic deformation appeared predominantly localized in the defect-free cleared channels following post-irradiation testing and hardly any dislocations were seen outside the channels. The microstructures following in-reactor tests were characterized by a small amount of cleared channels and a distinct dislocation density within the matrix. However, the dislocations observed following in-reactor testing did not seem to interact with each other, whereas that was the main mode of deformation in the non-irradiated reference sample. The possible mechanisms of plastic deformation are discussed based on the experimental results

    U2 - 10.1016/j.jnucmat.2012.10.014

    DO - 10.1016/j.jnucmat.2012.10.014

    M3 - Article

    VL - 442

    SP - S821-S825

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    IS - 1-3 suppl.1

    ER -