Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop

Ignas Mickus, Jari Lappalainen, Pavel Kudinov

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    APROS is a multifunctional simulator, suitable for various tasks throughout the complete power plant life cycle from design to operator training. The code combines the System-Thermal Hydraulics (STH) capabilities with 1D/3D reactor core neutronics and full automation system modelling. APROS is widely used for dynamic studies in light water nuclear reactor technology. Currently the simulation capabilities of the code are being developed for evaluation of Generation IV nuclear reactor designs that use liquid metals (e.g. Lead-Bismuth Eutectic (LBE) alloy) as cooling media. However, validation of APROS code has been limited to light water cooled systems (test facilities and reactors). Therefore validation is required for the LBE thermal-hydraulic models. In this work, we use data from the Thermal-hydraulic Accelerator-Driven System (ADS) Lead bismuth Loop (TALL) facility constructed at KTH. In total, 10 transient data sets from TALL experiments were used for APROS LBE fluid model integral validation. TALL facility model consisting of the primary LBE loop, the secondary oil loop and the ultimate water heat sink was developed using APROS Graphical User Interface (GUI). Five System Response Quantities (SRQs) were considered in the validation process: LBE temperatures at four locations of the facility and the LBE mass flow. Uncertainty analysis was employed in the validation process. Results of quantitative code validation are presented in the paper. Suggestions for improvements of the validation methodology, experimental conditions and approaches to reduction of experimental uncertainty are discussed in detail.
    Original languageEnglish
    Title of host publicationICAPP 2015 Proceedings
    Subtitle of host publication2015 International Congress on Advances in Nuclear Power Plants
    Publication statusPublished - 2015
    MoE publication typeNot Eligible
    EventInternational Congress on Advances in Nuclear Power Plants, ICAPP 2015 - Nice, France
    Duration: 3 May 20156 May 2015

    Conference

    ConferenceInternational Congress on Advances in Nuclear Power Plants, ICAPP 2015
    Abbreviated titleICAPP 2015
    CountryFrance
    CityNice
    Period3/05/156/05/15

    Fingerprint

    Bismuth
    Eutectics
    Lead
    Hydraulics
    Hydraulic models
    Light water reactors
    Uncertainty analysis
    Reactor cores
    Heat sinks
    Nuclear reactors
    Graphical user interfaces
    Test facilities
    Hot Temperature
    Liquid metals
    Particle accelerators
    Water
    Life cycle
    Power plants
    Automation
    Simulators

    Cite this

    Mickus, I., Lappalainen, J., & Kudinov, P. (2015). Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop. In ICAPP 2015 Proceedings: 2015 International Congress on Advances in Nuclear Power Plants [15178]
    Mickus, Ignas ; Lappalainen, Jari ; Kudinov, Pavel. / Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop. ICAPP 2015 Proceedings: 2015 International Congress on Advances in Nuclear Power Plants. 2015.
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    title = "Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop",
    abstract = "APROS is a multifunctional simulator, suitable for various tasks throughout the complete power plant life cycle from design to operator training. The code combines the System-Thermal Hydraulics (STH) capabilities with 1D/3D reactor core neutronics and full automation system modelling. APROS is widely used for dynamic studies in light water nuclear reactor technology. Currently the simulation capabilities of the code are being developed for evaluation of Generation IV nuclear reactor designs that use liquid metals (e.g. Lead-Bismuth Eutectic (LBE) alloy) as cooling media. However, validation of APROS code has been limited to light water cooled systems (test facilities and reactors). Therefore validation is required for the LBE thermal-hydraulic models. In this work, we use data from the Thermal-hydraulic Accelerator-Driven System (ADS) Lead bismuth Loop (TALL) facility constructed at KTH. In total, 10 transient data sets from TALL experiments were used for APROS LBE fluid model integral validation. TALL facility model consisting of the primary LBE loop, the secondary oil loop and the ultimate water heat sink was developed using APROS Graphical User Interface (GUI). Five System Response Quantities (SRQs) were considered in the validation process: LBE temperatures at four locations of the facility and the LBE mass flow. Uncertainty analysis was employed in the validation process. Results of quantitative code validation are presented in the paper. Suggestions for improvements of the validation methodology, experimental conditions and approaches to reduction of experimental uncertainty are discussed in detail.",
    author = "Ignas Mickus and Jari Lappalainen and Pavel Kudinov",
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    Mickus, I, Lappalainen, J & Kudinov, P 2015, Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop. in ICAPP 2015 Proceedings: 2015 International Congress on Advances in Nuclear Power Plants., 15178, International Congress on Advances in Nuclear Power Plants, ICAPP 2015, Nice, France, 3/05/15.

    Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop. / Mickus, Ignas; Lappalainen, Jari; Kudinov, Pavel.

    ICAPP 2015 Proceedings: 2015 International Congress on Advances in Nuclear Power Plants. 2015. 15178.

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    TY - GEN

    T1 - Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop

    AU - Mickus, Ignas

    AU - Lappalainen, Jari

    AU - Kudinov, Pavel

    N1 - Project : 87344 Project : 88918

    PY - 2015

    Y1 - 2015

    N2 - APROS is a multifunctional simulator, suitable for various tasks throughout the complete power plant life cycle from design to operator training. The code combines the System-Thermal Hydraulics (STH) capabilities with 1D/3D reactor core neutronics and full automation system modelling. APROS is widely used for dynamic studies in light water nuclear reactor technology. Currently the simulation capabilities of the code are being developed for evaluation of Generation IV nuclear reactor designs that use liquid metals (e.g. Lead-Bismuth Eutectic (LBE) alloy) as cooling media. However, validation of APROS code has been limited to light water cooled systems (test facilities and reactors). Therefore validation is required for the LBE thermal-hydraulic models. In this work, we use data from the Thermal-hydraulic Accelerator-Driven System (ADS) Lead bismuth Loop (TALL) facility constructed at KTH. In total, 10 transient data sets from TALL experiments were used for APROS LBE fluid model integral validation. TALL facility model consisting of the primary LBE loop, the secondary oil loop and the ultimate water heat sink was developed using APROS Graphical User Interface (GUI). Five System Response Quantities (SRQs) were considered in the validation process: LBE temperatures at four locations of the facility and the LBE mass flow. Uncertainty analysis was employed in the validation process. Results of quantitative code validation are presented in the paper. Suggestions for improvements of the validation methodology, experimental conditions and approaches to reduction of experimental uncertainty are discussed in detail.

    AB - APROS is a multifunctional simulator, suitable for various tasks throughout the complete power plant life cycle from design to operator training. The code combines the System-Thermal Hydraulics (STH) capabilities with 1D/3D reactor core neutronics and full automation system modelling. APROS is widely used for dynamic studies in light water nuclear reactor technology. Currently the simulation capabilities of the code are being developed for evaluation of Generation IV nuclear reactor designs that use liquid metals (e.g. Lead-Bismuth Eutectic (LBE) alloy) as cooling media. However, validation of APROS code has been limited to light water cooled systems (test facilities and reactors). Therefore validation is required for the LBE thermal-hydraulic models. In this work, we use data from the Thermal-hydraulic Accelerator-Driven System (ADS) Lead bismuth Loop (TALL) facility constructed at KTH. In total, 10 transient data sets from TALL experiments were used for APROS LBE fluid model integral validation. TALL facility model consisting of the primary LBE loop, the secondary oil loop and the ultimate water heat sink was developed using APROS Graphical User Interface (GUI). Five System Response Quantities (SRQs) were considered in the validation process: LBE temperatures at four locations of the facility and the LBE mass flow. Uncertainty analysis was employed in the validation process. Results of quantitative code validation are presented in the paper. Suggestions for improvements of the validation methodology, experimental conditions and approaches to reduction of experimental uncertainty are discussed in detail.

    M3 - Conference article in proceedings

    SN - 978-1-4951-6285-5

    BT - ICAPP 2015 Proceedings

    ER -

    Mickus I, Lappalainen J, Kudinov P. Validation of APROS code against experimental data from a Lead-Bismuth Eutectic thermal-hydraulic loop. In ICAPP 2015 Proceedings: 2015 International Congress on Advances in Nuclear Power Plants. 2015. 15178