Modeling of Zircaloy cladding primary creep during load drop and reversal

Ville Tulkki (Corresponding Author), Timo Ikonen

    Research output: Contribution to journalArticleScientificpeer-review

    6 Citations (Scopus)

    Abstract

    Modeling fuel behavior requires an accurate description of the cladding stress response for both operational and safety considerations. The transient creep response of Zirconium alloys is commonly modeled using a strain hardening rule which is known to hold in cases with monotonously increasing stresses. However, the strain hardening rule is experimentally known to fail in scenarios such as load drop or reversal. In this paper we derive a simple and easily implementable set of rules for primary creep based on experimental results which contradict the strain hardening rule. The primary creep predicted by these rules is compared with data from published thermal creep experiments and Halden in-pile creep experiment IFA-585. The model thus created is shown to perform well in describing both transient stress scenarios with monotonously increasing stress and scenarios involving load drops and reversals.
    Original languageEnglish
    Pages (from-to)98 - 103
    JournalJournal of Nuclear Materials
    Volume445
    DOIs
    Publication statusPublished - 2014
    MoE publication typeA1 Journal article-refereed

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    Creep
    strain hardening
    Strain hardening
    zirconium alloys
    Zirconium alloys
    piles
    Piles
    Loads (forces)
    safety
    Experiments

    Cite this

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    title = "Modeling of Zircaloy cladding primary creep during load drop and reversal",
    abstract = "Modeling fuel behavior requires an accurate description of the cladding stress response for both operational and safety considerations. The transient creep response of Zirconium alloys is commonly modeled using a strain hardening rule which is known to hold in cases with monotonously increasing stresses. However, the strain hardening rule is experimentally known to fail in scenarios such as load drop or reversal. In this paper we derive a simple and easily implementable set of rules for primary creep based on experimental results which contradict the strain hardening rule. The primary creep predicted by these rules is compared with data from published thermal creep experiments and Halden in-pile creep experiment IFA-585. The model thus created is shown to perform well in describing both transient stress scenarios with monotonously increasing stress and scenarios involving load drops and reversals.",
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    language = "English",
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    Modeling of Zircaloy cladding primary creep during load drop and reversal. / Tulkki, Ville (Corresponding Author); Ikonen, Timo.

    In: Journal of Nuclear Materials, Vol. 445, 2014, p. 98 - 103.

    Research output: Contribution to journalArticleScientificpeer-review

    TY - JOUR

    T1 - Modeling of Zircaloy cladding primary creep during load drop and reversal

    AU - Tulkki, Ville

    AU - Ikonen, Timo

    PY - 2014

    Y1 - 2014

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    AB - Modeling fuel behavior requires an accurate description of the cladding stress response for both operational and safety considerations. The transient creep response of Zirconium alloys is commonly modeled using a strain hardening rule which is known to hold in cases with monotonously increasing stresses. However, the strain hardening rule is experimentally known to fail in scenarios such as load drop or reversal. In this paper we derive a simple and easily implementable set of rules for primary creep based on experimental results which contradict the strain hardening rule. The primary creep predicted by these rules is compared with data from published thermal creep experiments and Halden in-pile creep experiment IFA-585. The model thus created is shown to perform well in describing both transient stress scenarios with monotonously increasing stress and scenarios involving load drops and reversals.

    U2 - 10.1016/j.jnucmat.2013.10.053

    DO - 10.1016/j.jnucmat.2013.10.053

    M3 - Article

    VL - 445

    SP - 98

    EP - 103

    JO - Journal of Nuclear Materials

    JF - Journal of Nuclear Materials

    SN - 0022-3115

    ER -