Böttcher, Michael

Jäger, Wadim

Stieglitz, Robert

English

KITopen

KIT – University of the State of Baden-Wuerttemberg and National Research Center of the Helmholtz AssociationInstitute for Neutron Physics and Reactor Technologywww.kit.eduKIT activities for Verification & Validation of Liquid Metals Thermal Hydraulics• CFX + variable turbulent Pr number• TRACE + empirical modelsMichael Boettcher, Wadim Jaeger, Robert StieglitzKarlsruhe Institute of Technology, Institute for Neutron Physics and Reactor TechnologyInstitute for Neutron Physics and Reactor Technology2 21.06.2016MotivationAt the INR a large sodium loop (7 m³; 37m total length, up to 150 m³/h) is underconstruction along with smaller liquidmetal cooled loops.Furthermore, other liquid metal cooledfacilities exist at the KIT (e.g. KALLA).In addition, the INR is involved in severalEuropean projects for liquid metal cooledfacilities/reactors (e.g. MYRRHA).Therefore, validated tools are needed forthe design, operation and demonstrationof safety of these loops/plants.KArlsruhe SOdium LAboratory - KASOLAV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology3 21.06.2016Turbulent Prandtl Number Concept= f(y+, Re, Pr,…)   (1)DNS of 2D channel flow Idea:Prt from DNS/LES dataas 3D look-up tables byTri-linear Interpolationand use them for similarflow types !Very difficult to obtain from measurements especially for liquid metal flows ! ᶹturb by RANS turbulence modelsλturb by (1) and look-up tablesData extension until Re=82000 by Duponcheel et. al.V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology4 21.06.20162D channel flowRe = 5600, 22000Pr = 0.01, 0.1, 1DNS/LES dataNo buoyancyPipe flowRe = 5700 … 111000Pr = 0.016 …0.0046Standard correlationsBuoyancy includedGap flowsingle pinRe = 33000 … 400000Pr ~ 0.016 (LBE flow)Detailed measurementsRod bundle flowPin assemblyRe = 7800 … 78000Pr ~ 0.016 (LBE flow)OECD correlation andmeasurementsValidation CasesV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology5 21.06.2016Validation case:Pipeflow with constant heat fluxCFX-model: 89000 cellsY+ = 0.3 …7  D = 9.5mm  L = 1.25mT0 Fully developed flowΔT≈const.zTValidation Cases: Pipe FlowV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology6 21.06.2016Validation Cases: Single PinModel informations:569 000 elements (16 cells in circumferential direction), structuredSST turbulence modelBuoyancy model with production anddissipation of turbulenceConjugate heat transfer (pin)Boundary conditions:InletVelocity profile (equilibrium) Constant inlet temperature T0Constant turbulence quantities (1%)OutletΔp=0 [Pa] at the outletPin surfaceHeat flux; pin head: heat flux derivedfrom measurementsOther surfacesadiabaticV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology7 21.06.2016Validation Cases: Single PinV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology8 21.06.201619 pins11.48 mm pitchLength ~1.3 m3 SpacersKALLA – Karlsruher liquid metal laboratoryTHEADES - Thermalhydraulics and ADS DesignTemperature 190°C-450°CFlow rate 47 m3/hPressure 5.9 barHeating 0.43 MW Source:T.Wetzel et. al, IKET3 SpacerinletoutletValidation Cases: Rod BundleV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology9 21.06.2016Validation Cases: Rod BundleTools:Pointwise V17.1 R4ANSYS CFX 14.0Details:33.6 Mio cellsFull structured, 120° partHeat conduction in spacersand rod clads0.01 mm spacing at heated surf.QI-RS turbulence model24 CPU-h for steady stateCenter ofa spacerV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology10 21.06.2016Validation Cases: Rod BundleRe=7700Re=77000Lower Re:Significantly thickerthermal layersPrt>1 for most centralsubchannel regionsHigher Re:Thinner thermal layersHigher y+ Prt <1 at centralsubchannelsV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology11 21.06.2016.. . .OECD Handbook:Re = 34958T0 = 473KQ = 173000 W/m2Validation Cases: Rod BundleV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology12 21.06.2016TRACE Closure Models The standard TRACE code (water with liquid and vapor phase) requires 10 parameters in order to close the field equations. For single phase liquid metal flow only two parameters are needed.Wall-to-liquid drag coefficientWall-to-fluid heat transfer coefficientV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology13 21.06.2016TRACE Closure Models TRACE LMV&VHeat TransferWall Drag∙∆ 2 ∙ ∙ ∙Form Loss Coefficient Friction FactorModels for low Prandtl number fluids are identical to the ones of mediums with Pr ≈ 1 Implementation of newmodels is not necessary!Models for low Prandtl number fluids differ considerably from fluids with Pr ≈ 1 Implementation of new models is necessary!V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology14 21.06.2016Liquid MetalsOriginal Version• Sodium (Na)• Lead-Bismuth-Eutectics (PbBi)1st Modification• Lead (Pb)• Lead-Bismuth-Eutectics (PbBi)2nd Modification• Potassium (K)• Sodium-Potassium Alloy (NaK)• Mercury (Hg)3rd Modification• Lithium (Li)• Lithium-Lead Alloy (LiPb)• Indium-Gallium-Tin Alloy (InGaSn)Jaeger, W. & Sánchez Espinoza, V.H., "Improvements and Validation of theSystem Code TRACE for Lead and Lead-Alloy Cooled Fast Reactors Safety-Related Investigations.", NUREG/IA-0421. Office of Nuclear RegulatoryResearch, U.S. Nuclear Regulatory Commission, Washington, DC, 2013.Jaeger, W., Hering, W., Diez de los Rios, N. & Gonzalez, A., "Validation ofTRACE in the field of liquid metal heat transfer.", Proceedings of: ASME2014 International Mechanical Engineering Congress and Exposition(IMECE2014). Montreal, Canada, 2014.V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology15 21.06.2016Liquid MetalsV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology16 21.06.2016Wall Drag: LACANES Benchmark 1/2Jaeger, W. & Sánchez Espinoza, V.H., "Improvements and Validation of the System Code TRACE for Lead and Lead-Alloy Cooled Fast ReactorsSafety-Related Investigations.", NUREG/IA-0421. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC.V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology17 21.06.2016Wall Drag: LACANES Benchmark 2/2Jaeger, W. & Sánchez Espinoza, V.H., "Improvements and Validation of the System Code TRACE for Lead and Lead-Alloy Cooled Fast ReactorsSafety-Related Investigations.", NUREG/IA-0421. Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC.V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology18 21.06.2016Wall Drag: KASOLA 1/2Jaeger, W., Homann, Ch., Hering, W. & Jammot, V., "Preparation of KASOLA Scientific Work Program using TRACE.",International Congress on Advances in Nuclear Power Plants (ICAPP2014). Charlotte, U.S.A., 2014.V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology19 21.06.2016Wall Drag: KASOLA 2/2V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology20 21.06.20160,0E+005,0E+041,0E+051,5E+052,0E+052,5E+053,0E+050 20000 40000 60000 80000 100000Pressure drop [Pa]Reynolds number [-]Experiment @ 200°CTRACE @ 200°CExperiment @ 350°CTRACE @ 350°CWall Drag: KALLA Rod Bundle – BundleJaeger, W., Boettcher, M. & Sánchez Espinoza, V.H., "Thermal-Hydraulic Evaluation of an LBE Cooled 19 Pin Bundle in theFrame of TRACE Validation.", International Conference on Nuclear Engineering (ICONE21). Chengdu, China, 2013.V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology21 21.06.20160,E+001,E+042,E+043,E+044,E+045,E+046,E+047,E+0410000 20000 30000 40000 50000 60000 70000 80000 90000Pressure drop [Pa]Reynolds number [-]Experiment spacer 1 @ 200°CExperiment spacer 2 @ 200°CExperiment spacer 3 @ 200°CExperiment spacer 1 @ 350°CExperiment spacer 2 @ 350°CExperiment spacer 3 @ 350°CSpacer 1 causes much higher pressure drops than spacers 2 & 3. From the theoretical point of view it seems to be impossible since the thermodynamic and fluid dynamic properties are identical at all three elevations. The reason for the higher pressure drop might be a plugging of the first spacer with oxidation products increasing the blockage ratio from originally 0.46 to roughly 0.70.Wall Drag: KALLA Rod Bundle – Spacers (1/2)Jaeger, W., Boettcher, M. & Sánchez Espinoza, V.H., "Thermal-Hydraulic Evaluation of an LBE Cooled 19 Pin Bundle in theFrame of TRACE Validation.", International Conference on Nuclear Engineering (ICONE21). Chengdu, China, 2013.V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology22 21.06.20160,E+001,E+042,E+043,E+044,E+045,E+046,E+047,E+0410000 20000 30000 40000 50000 60000 70000 80000 90000Pressure drop [Pa]Reynolds number [-]Experiment spacer 1 @200°CExperiment spacer 2 @200°CExperiment spacer 3 @200°CTRACE spacer 1 @ 200°CTRACE spacer 2 & 3 @200°CWall Drag: KALLA Rod Bundle – Spacers (2/2)Jaeger, W., Boettcher, M. & Sánchez Espinoza, V.H., "Thermal-Hydraulic Evaluation of an LBE Cooled 19 Pin Bundle in theFrame of TRACE Validation.", International Conference on Nuclear Engineering (ICONE21). Chengdu, China, 2013.V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology23 21.06.2016Wall Drag: Rectangular ChannelsV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology24 21.06.2016Liquid Metal Heat TransferR. Stieglitz, “Low Prandtl NumberThermal-Hydraulics“, In “Handbook onLead-bismuth Eutectic Alloy and LeadProperties, Materials Compatibility,Thermal-hydraulics and Technologies,OECD/NEA, NEA No. 6195, 2007.Na: Pr ≈ 0.006Pb: Pr ≈ 0.02Air: Pr ≈ 0.71H2O: Pr ≈ 7.0Heat transfer to liquid metal ≠ Heat transfer to water.Characterization of heat transfer Prandtl number.Prandtl number = Ratio of the momentum and thermal diffusivity.Pr ≈ 1 Thermal boundary layer ≈ Velocity boundary layer.Liquid metals Pr << 1Thermal boundary layer >> Velocity boundary layerHeat diffusion >> Momentum diffusion.Heat conduction >> Heat convection.Pr∙V&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology25 21.06.2016FlowRegime/PhenomenaDuct Flow Bundle FlowForced convectionLaminar XTurbulent XTransition XMixed convectionLaminarTurbulentTransitionFree convectionLaminarTurbulentTransitionEntrance Length EffectVariable Property EffectLiquid Metal Heat Transfer – RegimesOriginal versionV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology26 21.06.2016FlowRegime/PhenomenaDuct Flow Bundle FlowForced convectionLaminar X X X XTurbulent X X X XTransition XMixed convectionLaminar XTurbulent XTransition XFree convectionLaminar -Turbulent XTransition -Entrance Length Effect X XVariable Property EffectLiquid Metal Heat Transfer – RegimesModified versionV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology27 21.06.2016FlowRegime/PhenomenaDuct Flow Bundle FlowForced convectionLaminar Const. Jaeger Jaeger Const.Turbulent Stupinski Jaeger Jaeger UshakovTransition Stupinski UshakovMixed convectionLaminar CubicTurbulent CubicTransition CubicFree convectionLaminarTurbulent HymanTransitionEntrance Length Effect Das JaegerVariable Property EffectLiquid Metal Heat Transfer – ModelsModified versionV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology28 21.06.2016Liquid Metal Heat Transfer – PipeV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology29 21.06.2016Liquid Metal Heat Transfer – PipeV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology30 21.06.2016Liquid Metal Heat Transfer – RectangularV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology31 21.06.2016Liquid Metal Heat Transfer – RectangularV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology32 21.06.2016Liquid Metal Heat Transfer – Parallel PlateV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology33 21.06.2016Liquid Metal Heat Transfer – Parallel PlateV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology34 21.06.2016Liquid Metal Heat Transfer – AnnularV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology35 21.06.2016Liquid Metal Heat Transfer – AnnularV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology36 21.06.2016Liquid Metal Heat Transfer – Rod BundleV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology37 21.06.2016Liquid Metal Heat Transfer – Rod BundleV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology38 21.06.2016Liquid Metal Heat Transfer – ApplicationV&V Workshop, July 5-6, KTH StockholmInstitute for Neutron Physics and Reactor Technology39 21.06.2016Summary & ConclusionReview Development Validation ApplicationEmpirical (system code) and turbulent Prandtl number look-up tables (CFD) developed for forced convection flows of liquid metalsValidation process shows good agreement to reference dataEasy to implement in other system codes and CFD codesMore experimental data and DNS/LES data are required to continue the validation process for mixed and natural convection flowsV&V Workshop, July 5-6, KTH Stockholm

KIT activities for verification and validation of liquid metals thermal hydraulics

https://publikationen.bibliothek.kit.edu/1000060090/3912713

KIT activities for verification and validation of liquid metals thermal hydraulics

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