Validation of the reactor dynamics code TRAB

Hanna Räty, Riitta Kyrki-Rajamäki, Rajamäki Markku

    Research output: Book/ReportReport

    Abstract

    The one-dimensional reactor dynamics code TRAB (Transient Analysis code for BWRS) developed at VTT was originally designed for BWR analyses, but it can in its present version be used for various modelling purposes. The core model of TRAB can be used separately for LWR calculations. For PWR modelling the core model of TRAB has been coupled to circuit model SMABRE to form the SMATRA code. The versatile modelling capabilities of TRAB have been utilised also in analyses of e.g. the heating reactor SECURE and the RBMK-type reactor (Chernobyl). This report summarises the extensive validation of TRAB. TRAB has been validated with benchmark problems, comparative calculations against independent analyses, analyses of start-up experiments of nuclear power plants and real plant transients. Comparative RBMK type reactor calculations have been made against Soviet simulations and the initial power excursion of the Chernobyl reactor accident has also been calculated with TRAB. TRAB has been extensively used for analyses of the TVO ABB Atom type BWR reactors and within SMATRA for PWR analyses of the Loviisa VVER-440 reactors and VVER-91 type reactors. TRAB is also used outside VTT both for BWR analyses and, within SMATRA, for PWR analyses by the Finnish Centre for Radiation and Nuclear Safety (STUK) and the Imatran Voima Oy (IVO) power company.
    Original languageEnglish
    Place of PublicationEspoo
    PublisherVTT Technical Research Centre of Finland
    Number of pages31
    ISBN (Print)951-38-3976-1
    Publication statusPublished - 1991
    MoE publication typeD4 Published development or research report or study

    Publication series

    SeriesValtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports
    Number729
    ISSN0358-5077

    Fingerprint

    Transient analysis
    Boiling water reactors
    Nuclear power plants
    Accidents
    Radiation
    Heating
    Atoms
    Networks (circuits)

    Keywords

    • validation
    • one-dimensional reactor dynamics
    • space-time kinetics
    • reactor safety analysis
    • reactor accidents
    • thermohydraulics
    • TRAB

    Cite this

    Räty, H., Kyrki-Rajamäki, R., & Markku, R. (1991). Validation of the reactor dynamics code TRAB. Espoo: VTT Technical Research Centre of Finland. Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports, No. 729
    Räty, Hanna ; Kyrki-Rajamäki, Riitta ; Markku, Rajamäki. / Validation of the reactor dynamics code TRAB. Espoo : VTT Technical Research Centre of Finland, 1991. 31 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 729).
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    Räty, H, Kyrki-Rajamäki, R & Markku, R 1991, Validation of the reactor dynamics code TRAB. Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports, no. 729, VTT Technical Research Centre of Finland, Espoo.

    Validation of the reactor dynamics code TRAB. / Räty, Hanna; Kyrki-Rajamäki, Riitta; Markku, Rajamäki.

    Espoo : VTT Technical Research Centre of Finland, 1991. 31 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 729).

    Research output: Book/ReportReport

    TY - BOOK

    T1 - Validation of the reactor dynamics code TRAB

    AU - Räty, Hanna

    AU - Kyrki-Rajamäki, Riitta

    AU - Markku, Rajamäki

    PY - 1991

    Y1 - 1991

    N2 - The one-dimensional reactor dynamics code TRAB (Transient Analysis code for BWRS) developed at VTT was originally designed for BWR analyses, but it can in its present version be used for various modelling purposes. The core model of TRAB can be used separately for LWR calculations. For PWR modelling the core model of TRAB has been coupled to circuit model SMABRE to form the SMATRA code. The versatile modelling capabilities of TRAB have been utilised also in analyses of e.g. the heating reactor SECURE and the RBMK-type reactor (Chernobyl). This report summarises the extensive validation of TRAB. TRAB has been validated with benchmark problems, comparative calculations against independent analyses, analyses of start-up experiments of nuclear power plants and real plant transients. Comparative RBMK type reactor calculations have been made against Soviet simulations and the initial power excursion of the Chernobyl reactor accident has also been calculated with TRAB. TRAB has been extensively used for analyses of the TVO ABB Atom type BWR reactors and within SMATRA for PWR analyses of the Loviisa VVER-440 reactors and VVER-91 type reactors. TRAB is also used outside VTT both for BWR analyses and, within SMATRA, for PWR analyses by the Finnish Centre for Radiation and Nuclear Safety (STUK) and the Imatran Voima Oy (IVO) power company.

    AB - The one-dimensional reactor dynamics code TRAB (Transient Analysis code for BWRS) developed at VTT was originally designed for BWR analyses, but it can in its present version be used for various modelling purposes. The core model of TRAB can be used separately for LWR calculations. For PWR modelling the core model of TRAB has been coupled to circuit model SMABRE to form the SMATRA code. The versatile modelling capabilities of TRAB have been utilised also in analyses of e.g. the heating reactor SECURE and the RBMK-type reactor (Chernobyl). This report summarises the extensive validation of TRAB. TRAB has been validated with benchmark problems, comparative calculations against independent analyses, analyses of start-up experiments of nuclear power plants and real plant transients. Comparative RBMK type reactor calculations have been made against Soviet simulations and the initial power excursion of the Chernobyl reactor accident has also been calculated with TRAB. TRAB has been extensively used for analyses of the TVO ABB Atom type BWR reactors and within SMATRA for PWR analyses of the Loviisa VVER-440 reactors and VVER-91 type reactors. TRAB is also used outside VTT both for BWR analyses and, within SMATRA, for PWR analyses by the Finnish Centre for Radiation and Nuclear Safety (STUK) and the Imatran Voima Oy (IVO) power company.

    KW - validation

    KW - one-dimensional reactor dynamics

    KW - space-time kinetics

    KW - reactor safety analysis

    KW - reactor accidents

    KW - thermohydraulics

    KW - TRAB

    M3 - Report

    SN - 951-38-3976-1

    T3 - Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports

    BT - Validation of the reactor dynamics code TRAB

    PB - VTT Technical Research Centre of Finland

    CY - Espoo

    ER -

    Räty H, Kyrki-Rajamäki R, Markku R. Validation of the reactor dynamics code TRAB. Espoo: VTT Technical Research Centre of Finland, 1991. 31 p. (Valtion teknillinen tutkimuskeskus. Tutkimuksia - Research Reports; No. 729).