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.",
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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

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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