Albrecht, O.

Hering, W.

Häfner, U.

Onea, A.

Stieglitz, Robert

Vielhaber, S.

Weisenburger, A.

KITopen

KIT – The Research University in the Helmholtz AssociationInstitute for Neutron Physics and Reactor Technologywww.kit.eduInitial tests of the high temperature SOLTEC facility for corrosion analysesA. Onea, W. Hering, A. Weisenburger, S. Vielhaber, O. Albrecht, U. Häfner, R. Stieglitz2 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologyOutlineIntroductionLiquid metals facilities at KIT-INRSOLTEC family (SOdium Loop to TEst Corrosion and materials):ObjectivesMain technical dataSafety issuesP&I diagrammTest sectionsNumerical analyses and experimental testsOperational experience3 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologyLIMTECH AllianceHEMCP:Helmholtz Energy Materials Characterization PlatformCSP concept* of  solar tower plant with Na as HTF and AMTEC technology as topping cycle  R&D on materials and components *W. Hering et al. – Europ. Ph. J.  33, 03003 (2012)**Developed in the frame of the Helmholtz Energy Material Characterization Platform (HEMCP) and Helmholtz Alliance on Liquid Metal Technology (LIMTECH) Main tasks for the SOLTEC family: Development of the 1000 K sodium SOLTEC test facilities (INR)**Material qualification for high temperature applications (collaborations with IAM-AWP, IHM)Soltec-1: Creep fatigue tests of innovative materials in hot Na (unique)Soltec-2: Corrosion/erosion tests for new steels in hot Na Soltec-3: Long term tests for new thermoelectrical convertersIntroduction4 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologyNa – Facilities: Operating, Qualifying, Preparation, DesignBasic physics (Electro-chemistry) System level (Materials) Medium Scale / DemonstratorAMTECATEFA  DITEFA KARIFA„Energy“ - materialsSOLTEC 1AWP – 2IHMSOLTEC 3INRCORTINAAWPThermal storage: KASOLA facilityMHDPumpNa-receiver5 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologyStatus of HAC / KASOLA facilities  Facility Fluid Max. temp. [°C]StatusKASOLA Na; ~7 to 550 In HT qualification phaseATEFA Na~3 L 1000Successfully operated up to 700°C; PhD finished.SOLTEC-2 Na~14 L 720Qualification phase with sodium up to700°CSOLTEC-1 Na~14 L 720 In final assembly phaseSOLTEC-3 Na~14 L 950Finalization postponed until Q4/19Commissioning in Q1/20DITEFA InGaSn In constructionKARIFA Na 1000 Concept finished & fixed  detail designOperating, Qualifying, Preparation, Design6 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologyR&D objectives SOLTEC-2Na inventory: ~ 14 LMass flow rate: 300 kg/h S1: 4.8 m/s in test sample S2: 1.1 m/s in test sampleTemperature: cold loop 700 K; hot loop 1000 KMax. pressure: 3.5 bar gPressure loss: S-1: ~ 1.6 bar; S-2: ~ 0.45 barTechnical dataMaterial development, qualification & durability at high temp. in contact with flowing liquid metals (Na, design complying also with PbBi, Sn), since no experimental data for steel corrosion in Na above 650°C is reportedSimulation of real operation condition (rapid temperature transients - Thermal cycling tests at high temperature DT: 650 – 900°C, LCF, safety & operational aspects (LOFA, LOHS)  Development, qualification & demonstration of Long term stability of protective surface coatings (in/outer surface) (using pulsed electron beams – Surface Optimization facility with Fast In-situ diagnostic Equipment- GESA-SOFIE)Planned materials: austenitic steels with different chrome composition, nickel-based superalloys, Inconel-based superalloys, W-Cu laminates.7 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologyLIMTECH AllianceHEMCP:Helmholtz Energy Materials Characterization PlatformCompact configuration: 1.2 × 1.6  × 1.9 m3Main components: Na-pump (3kW permanent magnet pump)7.5 kW Na-air HX coupled to a 27 kW Na-Na heat recuperator, Storage tank (15 L) used as expansion tank (particular feature)6.7 kW HT heaterMaterials: Inconel (HT side), 316Ti (LT side)Ar is used as cover gas to fill/drain the facility and pressure monitoringHeating power: ~40 kWPLS: Siemens Simantec S7Instrumentation: Na/Ar – pressure, temperature, Na-level meter, Na flowmeter Technical data (2)Manufacturing: SAAS GmbH, SOWEC GmbH8 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologySafety issuesDedicated infrastructure for LM facilities (KASOLA facility, LM lab)Fail safe design: Fast drainage is to be made at any malfunctionSample rupture: vacuum monitored in the test chamberHeater and pump to be stopped either by the process control system(PCS) or by signals from sensors operating separately from the PCSLimited amount of NaAr used as cover gas. All argon/sodium interfaces protected by filtersAll Na valves have a NO configurationLow overpressure in any operation stateAny leackage to be detected by the leackage detection systemNa collection tray integrated in the bottom part of the framework of the housingAny possible fire/smoke limited within the insulated metallic housing 03.07.20199 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologySOLTEC – SOdium Loop to TEst materials and CorrosionSOLTEC -1,-2 3D model1,2 m6.3 kW heater3kW Na pumpNa storage tanks (15 L)Main components1000 K700 KPiping and instrumentation diagram10 Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of TechnologySOLTEC – SOdium Loop to TEst materials and CorrosionInnovative W-Cu compounds*Zwick/Roell Z100 universal traction facility (Low cycle fatigue tests)Material test chamberSOLTEC - 1 SOLTEC - 2SOLTEC - 3*J. Reiser et al. - Advanced Eng. Mat. 17, 491 (2015)Test chamber for thermoelectric convertersTest sections:Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of Technology11Numerical analyses and experimental testsFEM analysis: Na-Na heat recuperator, Na-air HXCFD analysis: Na-Na heat recuperator, Na-air HX. Validation against heat balance analysisTRACE analysis: SOLTEC-1-2 drainage: high temperature region drained in < 30 sTransient and steady-state simulations: filling/drainage process, steady-state simulationsExperimental tests: Pressure tests of the maincomponents successfully performedExperimental tests of screwconnections03.07.201901020304050607080901000 20 40 60 80 100 120 140Time [s]Filllevel[%]Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of Technology12Numerical analyses and experimental testsTheoretical analyses*: Pressure loss: (good agreement with TRACE model)Heat balance analysis03.07.2019AnsatzS-1࢖ / Pa ࢖ / %Prandtl-Kármán1,62E+5 2,47Ghanbari 1,67E+5 5,39TRACE 1,58E+5 /D. Fischer – TRACE simulation SOLTEC-1, -2, KITLocationTemperature[°C] FEMTemperature[°C] TRACEࢀ ࢀ/ %Inlet Na-Na HX 420,00 419,94 -0,06 0,01Outlet Na-Na HX 689,80 715,56 +25,76 3,73Inlet Na-Air HX 740,00 740,20 +0,20 0,02Middle section Na-Air HX 469,50 444,52 -24,98 5,32Outlet Na-Air HX 388,80 378,85 -9,95 2,55 SOLTEC-1LocationTemperature[°C] FEMTemperature[°C] TRACEࢀ ࢀ[%]Inlet Na-Na HX 420,00 420,05 +0,05 0,01Outlet Na-Na HX 689,80 715,68 +25,9 3,75Inlet Na-Air HX 740,00 740,35 +0,35 0,05Middle section Na-Air HX 469,50 444,64 -24,86 5,29Outlet Na-Air HX 388,80 378.95 -9,85 2,53 SOLTEC-2Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of Technology13Results and operational experienceLoop evacuation prior to the loop fillingFilling under low Ar pressure and vacuumHT heater set to operational temperature once the loop is filledNa thermal expansion compensated in the STTemperature in the LT side < 450°CHT heater off / low power before drainage to avoid thermal shocks in the STNo leakage / fireHowever, one Na valve exchangeddue to plugging (replacement underAr atmosphere and at RT)03.07.2019Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of Technology14Temperature distibution03.07.2019Temperature in LT region < 550°CFast thermal transientsInstitute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of Technology15Pressure distribution03.07.2019Low pressure difference across the pumpLow pressure levels < 3.5 bar gInstitute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of Technology16Set-into-operation03.07.2019Institute for Neutron Physics and Reactor TechnologyKarlsruhe Institute of Technology17Looking forward for future collaborations!03.07.2019Friday, Session 1, C2, 10:00: A. Onea, W. Hering, S. Perez Martin, et al. - Numerical andexperimental investigations of temperature investigation in an AMTEC test cell

Initial tests of the SOLTEC-2 high temperature sodium facility for corrosion analyses

https://publikationen.bibliothek.kit.edu/1000096308/33847574

Initial tests of the SOLTEC-2 high temperature sodium facility for corrosion analyses

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