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
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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.",
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author = "Ignas Mickus and Kaspar K{\"o}{\"o}p and Marti Jeltsov and Dmitry Grishchenko and Pavel Kudinov and Jari Lappalainen",
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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