Development of tall-3D test matrix for apros code validation

Ignas Mickus, Kaspar Kööp, Marti Jeltsov, Dmitry Grishchenko, Pavel Kudinov, Jari Lappalainen

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

    Abstract

    APROS code is a multifunctional process simulator which combines System Thermal-Hydraulic (STH) capabilities with 1D/3D reactor core neutronics and full automation system modeling. It is applied for various tasks throughout the complete power plant life cycle including R&D, process and control engineering, and operator training. Currently APROS is being developed for evaluation of Generation IV conceptual designs using Lead-Bismuth Eutectic (LBE) alloy coolant. TALL-3D facility has been built at KTH in order to provide validation data for standalone and coupled STH and Computational Fluid Dynamics (CFD) codes. The facility consists of sections with measured inlet and outlet conditions for separate effect and integral effect tests (SETs and IETs). The design is aimed at reducing experimental uncertainties and allowing full separation of code validation from model input calibration. In this paper we present the development of experimental TALL-3D test matrix for comprehensive validation of APROS code. First, the representative separate effect and integral system response quantities (SRQs) are defined. Second, sources of uncertainties are identified and code sensitivity analysis is carried out to quantify the effects of code input uncertainties on the code prediction. Based on these results the test matrixes for calibration and validation experiments are determined in order to minimize the code input uncertainties. The applied methodology and the results are discussed in detail.
    Original languageEnglish
    Title of host publication16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16)
    PublisherAmerican Nuclear Society ANS
    Pages4562-4575
    Editioncd-rom
    ISBN (Print)978-1-5108-1184-3
    Publication statusPublished - 2015
    MoE publication typeA4 Article in a conference publication
    Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-16 - Chicago, United States
    Duration: 30 Aug 20154 Sep 2015
    Conference number: 16

    Conference

    Conference16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-16
    Abbreviated titleNURETH-16
    CountryUnited States
    CityChicago
    Period30/08/154/09/15

    Fingerprint

    Hydraulics
    Calibration
    Reactor cores
    Conceptual design
    Bismuth
    Coolants
    Eutectics
    Sensitivity analysis
    Life cycle
    Power plants
    Computational fluid dynamics
    Automation
    Lead
    Simulators
    Uncertainty
    Experiments
    Hot Temperature

    Keywords

    • generation IV
    • lead-bismuth eutectic
    • APROS
    • validation
    • dynamic process simulation

    Cite this

    Mickus, I., Kööp, K., Jeltsov, M., Grishchenko, D., Kudinov, P., & Lappalainen, J. (2015). Development of tall-3D test matrix for apros code validation. In 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (cd-rom ed., pp. 4562-4575). American Nuclear Society ANS.
    Mickus, Ignas ; Kööp, Kaspar ; Jeltsov, Marti ; Grishchenko, Dmitry ; Kudinov, Pavel ; Lappalainen, Jari. / Development of tall-3D test matrix for apros code validation. 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16). cd-rom. ed. American Nuclear Society ANS, 2015. pp. 4562-4575
    @inproceedings{4fa9f83f3dfd42419db41b2717c4ef8d,
    title = "Development of tall-3D test matrix for apros code validation",
    abstract = "APROS code is a multifunctional process simulator which combines System Thermal-Hydraulic (STH) capabilities with 1D/3D reactor core neutronics and full automation system modeling. It is applied for various tasks throughout the complete power plant life cycle including R&D, process and control engineering, and operator training. Currently APROS is being developed for evaluation of Generation IV conceptual designs using Lead-Bismuth Eutectic (LBE) alloy coolant. TALL-3D facility has been built at KTH in order to provide validation data for standalone and coupled STH and Computational Fluid Dynamics (CFD) codes. The facility consists of sections with measured inlet and outlet conditions for separate effect and integral effect tests (SETs and IETs). The design is aimed at reducing experimental uncertainties and allowing full separation of code validation from model input calibration. In this paper we present the development of experimental TALL-3D test matrix for comprehensive validation of APROS code. First, the representative separate effect and integral system response quantities (SRQs) are defined. Second, sources of uncertainties are identified and code sensitivity analysis is carried out to quantify the effects of code input uncertainties on the code prediction. Based on these results the test matrixes for calibration and validation experiments are determined in order to minimize the code input uncertainties. The applied methodology and the results are discussed in detail.",
    keywords = "generation IV, lead-bismuth eutectic, APROS, validation, dynamic process simulation",
    author = "Ignas Mickus and Kaspar K{\"o}{\"o}p and Marti Jeltsov and Dmitry Grishchenko and Pavel Kudinov and Jari Lappalainen",
    note = "Project : 104320",
    year = "2015",
    language = "English",
    isbn = "978-1-5108-1184-3",
    pages = "4562--4575",
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    Mickus, I, Kööp, K, Jeltsov, M, Grishchenko, D, Kudinov, P & Lappalainen, J 2015, Development of tall-3D test matrix for apros code validation. in 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16). cd-rom edn, American Nuclear Society ANS, pp. 4562-4575, 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-16, Chicago, United States, 30/08/15.

    Development of tall-3D test matrix for apros code validation. / Mickus, Ignas; Kööp, Kaspar; Jeltsov, Marti; Grishchenko, Dmitry; Kudinov, Pavel; Lappalainen, Jari.

    16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16). cd-rom. ed. American Nuclear Society ANS, 2015. p. 4562-4575.

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

    TY - GEN

    T1 - Development of tall-3D test matrix for apros code validation

    AU - Mickus, Ignas

    AU - Kööp, Kaspar

    AU - Jeltsov, Marti

    AU - Grishchenko, Dmitry

    AU - Kudinov, Pavel

    AU - Lappalainen, Jari

    N1 - Project : 104320

    PY - 2015

    Y1 - 2015

    N2 - APROS code is a multifunctional process simulator which combines System Thermal-Hydraulic (STH) capabilities with 1D/3D reactor core neutronics and full automation system modeling. It is applied for various tasks throughout the complete power plant life cycle including R&D, process and control engineering, and operator training. Currently APROS is being developed for evaluation of Generation IV conceptual designs using Lead-Bismuth Eutectic (LBE) alloy coolant. TALL-3D facility has been built at KTH in order to provide validation data for standalone and coupled STH and Computational Fluid Dynamics (CFD) codes. The facility consists of sections with measured inlet and outlet conditions for separate effect and integral effect tests (SETs and IETs). The design is aimed at reducing experimental uncertainties and allowing full separation of code validation from model input calibration. In this paper we present the development of experimental TALL-3D test matrix for comprehensive validation of APROS code. First, the representative separate effect and integral system response quantities (SRQs) are defined. Second, sources of uncertainties are identified and code sensitivity analysis is carried out to quantify the effects of code input uncertainties on the code prediction. Based on these results the test matrixes for calibration and validation experiments are determined in order to minimize the code input uncertainties. The applied methodology and the results are discussed in detail.

    AB - APROS code is a multifunctional process simulator which combines System Thermal-Hydraulic (STH) capabilities with 1D/3D reactor core neutronics and full automation system modeling. It is applied for various tasks throughout the complete power plant life cycle including R&D, process and control engineering, and operator training. Currently APROS is being developed for evaluation of Generation IV conceptual designs using Lead-Bismuth Eutectic (LBE) alloy coolant. TALL-3D facility has been built at KTH in order to provide validation data for standalone and coupled STH and Computational Fluid Dynamics (CFD) codes. The facility consists of sections with measured inlet and outlet conditions for separate effect and integral effect tests (SETs and IETs). The design is aimed at reducing experimental uncertainties and allowing full separation of code validation from model input calibration. In this paper we present the development of experimental TALL-3D test matrix for comprehensive validation of APROS code. First, the representative separate effect and integral system response quantities (SRQs) are defined. Second, sources of uncertainties are identified and code sensitivity analysis is carried out to quantify the effects of code input uncertainties on the code prediction. Based on these results the test matrixes for calibration and validation experiments are determined in order to minimize the code input uncertainties. The applied methodology and the results are discussed in detail.

    KW - generation IV

    KW - lead-bismuth eutectic

    KW - APROS

    KW - validation

    KW - dynamic process simulation

    M3 - Conference article in proceedings

    SN - 978-1-5108-1184-3

    SP - 4562

    EP - 4575

    BT - 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16)

    PB - American Nuclear Society ANS

    ER -

    Mickus I, Kööp K, Jeltsov M, Grishchenko D, Kudinov P, Lappalainen J. Development of tall-3D test matrix for apros code validation. In 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16). cd-rom ed. American Nuclear Society ANS. 2015. p. 4562-4575