Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core

Elina Syrjälahti (Corresponding Author), Timo Ikonen, Ville Tulkki

    Research output: Contribution to journalArticleResearchpeer-review

    Abstract

    This paper describes the simplified model for burnup-induced fuel rod deformations occurring during base irradiation period, from manufacturing to the beginning of the transient. Model is intended to be used together with a codes that are used for analysis of whole core and plant transients. Model consist of thermal and mechanical parts. Due to the high conductance approximation for the gap conductance, the thermal part of the model can be solved independently from the mechanical model. In this way the use of iterative solvers is avoided and model is simple to implement. Model is verified against FRAPCON simulations and has been integrated to the reactor dynamics code HEXTRAN, in which it provides initial data for fuel behavior module FINIX for transient simulation. Effect of burnup initialization on simulation of reactor transients has been demonstrated with the reactor dynamics code HEXTRAN that uses FINIX as a fuel behavior module.
    LanguageEnglish
    Pages121-131
    Number of pages11
    JournalAnnals of Nuclear Energy
    Volume125
    DOIs
    Publication statusPublished - 2019
    MoE publication typeNot Eligible

    Fingerprint

    Reactor cores
    Irradiation

    Keywords

    • Fuel rod behavior
    • Nuclear fuel modeling
    • Reactor dynamics
    • FINIX
    • HEXTRAN

    OKM Publication Types

    • A1 Refereed journal article

    OKM Open Access Status

    • 0 Not Open Access

    ASJC Scopus subject areas

    • Nuclear Energy and Engineering

    Cite this

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    title = "Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core",
    abstract = "This paper describes the simplified model for burnup-induced fuel rod deformations occurring during base irradiation period, from manufacturing to the beginning of the transient. Model is intended to be used together with a codes that are used for analysis of whole core and plant transients. Model consist of thermal and mechanical parts. Due to the high conductance approximation for the gap conductance, the thermal part of the model can be solved independently from the mechanical model. In this way the use of iterative solvers is avoided and model is simple to implement. Model is verified against FRAPCON simulations and has been integrated to the reactor dynamics code HEXTRAN, in which it provides initial data for fuel behavior module FINIX for transient simulation. Effect of burnup initialization on simulation of reactor transients has been demonstrated with the reactor dynamics code HEXTRAN that uses FINIX as a fuel behavior module.",
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    author = "Elina Syrj{\"a}lahti and Timo Ikonen and Ville Tulkki",
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    language = "English",
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    journal = "Annals of Nuclear Energy",
    issn = "0306-4549",
    publisher = "Elsevier",

    }

    Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core. / Syrjälahti, Elina (Corresponding Author); Ikonen, Timo; Tulkki, Ville.

    In: Annals of Nuclear Energy, Vol. 125, 2019, p. 121-131.

    Research output: Contribution to journalArticleResearchpeer-review

    TY - JOUR

    T1 - Modeling burnup-induced fuel rod deformations and their effect on transient behavior of a VVER-440 reactor core

    AU - Syrjälahti, Elina

    AU - Ikonen, Timo

    AU - Tulkki, Ville

    PY - 2019

    Y1 - 2019

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    AB - This paper describes the simplified model for burnup-induced fuel rod deformations occurring during base irradiation period, from manufacturing to the beginning of the transient. Model is intended to be used together with a codes that are used for analysis of whole core and plant transients. Model consist of thermal and mechanical parts. Due to the high conductance approximation for the gap conductance, the thermal part of the model can be solved independently from the mechanical model. In this way the use of iterative solvers is avoided and model is simple to implement. Model is verified against FRAPCON simulations and has been integrated to the reactor dynamics code HEXTRAN, in which it provides initial data for fuel behavior module FINIX for transient simulation. Effect of burnup initialization on simulation of reactor transients has been demonstrated with the reactor dynamics code HEXTRAN that uses FINIX as a fuel behavior module.

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    KW - Reactor dynamics

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