German Experimental Activities for Advanced Modelling and Validation Relating to Containment Thermal Hydraulics and Source Term
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1 German Experimental Activities for Advanced Modelling and Validation Relating to Containment Thermal Hydraulics and Source Term H.-J. Allelein 1,2, S. Gupta 3, G. Poss 3, E.-A. Reinecke 2, F. Funke 4 1 RWTH Aachen University, 2 Forschungszentrum Jülich, 3 Becker Technologies, 4 AREVA GmbH IAEA Int. Conf. on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants (CN-251) Vienna, Austria, June 6-9, 2017
2 Outline German Experimental Activities for Advanced Modelling and Validation Relating to Containment Thermal Hydraulics and Source Term Background & Motivation Experimental activities Gas distribution and thermal hydraulics PAR operation under severe accident conditions Iodine and aerosol behavior Outlook 2
3 Background & Motivation 3 Severe accidents in LWRs are governed by thermal hydraulic processes, influencing safety relevant phenomena formation and distribution of flammable hydrogen/air mixtures fission product (aerosols, iodine) behavior International efforts are focused on the further development of computational methods and tools to predict accident phenomena and consequences to provide a reliable background for Severe Accident Management German institutions provide experimental facilities with high quality data bases for advanced code development and validation Forschungszentrum Jülich GmbH / RWTH Aachen University Becker Technologies GmbH AREVA GmbH
4 Gas distribution and thermal hydraulics Containments of large PWRs volume of up to 70,000 m³ different compartments housing the components of the reactor cooling system and auxiliary systems During DBA and BDBA, large quantities of steam and hydrogen as well as fission products are released from the break location into the containment. Detailed knowledge of the spatial distribution of gases and the atmospheric conditions is essential for safety system design and accident management, provides relevant information for subsequent analyses of possible hydrogen combustion loads and the impact on the radiological source term. 4
5 THAI + facility Operated by Becker Technologies in close co-operation with GRS (Cologne, Garching) and AREVA (Erlangen) Research goals: LWR containment safety research under severe accident conditions Dimensions and boundary conditions 80 m³ total gas volume, 11.3 m height, vessel diameters of 3.2 m (THAI) and 1.6 m (PAD) Design P/T: C Licensed for use of radiotracer I 123 Pressure resistant for H 2 deflagrations THAI Experimental program National projects running since 2000 OECD/NEA projects: THAI ( ), THAI-2 ( ), THAI-3 ( ) THAI Test data for code benchmarks in ISP-47&49, EU-SARNET/SARNET2 PAD 5
6 THAI/THAI + results: Thermal hydraulics/gas distribution Focus on inhomogeneous atmospheric conditions Formation and removal of light gas (e.g. He, H 2, steam) stratification Stepwise procedure to study turbulence, buoyancy and condensation effects Data continuously used for code benchmarking 6 THAI HM tests: confirmation of transferability of He results to H 2 distribution problems TH-27: Double-blind international code benchmark
7 6m SETCOM facility Investigation of wall condensation for CFD model development Condensation of steam/air mixtures on 6 m cooling plate Inclination between horizontal and vertical Non-intrusive measurements Velocity profile: Particle Image Velocimetry Laser Doppler Velocimetry Temperature/concentration profiles: Raman Rayleigh Spectroscopy 6m y 7
8 Ri+ SETCOM results: Wall condensation tests Forced convection flow conditions Successful verification of the experimental concept with well-known heat and mass transfer correlations Velocity measurements inside the condensing boundary layer First results for buoyancy-driven flows (mixed convection) Successful velocity measurements of condensing boundary layer Integration of mixed-convection data into CFD model development 8
9 PAR operation under severe accident conditions Passive auto-catalytic recombiners (PARs) are increasingly installed inside the containments of LWRs to remove hydrogen that may be released during a LOCA to avoid possible threats related to fast hydrogen deflagration PARs contribute to the containment thermal hydraulics by inducing heat and flow patterns promoting atmosphere mixing. Recently, research is focusing on PAR operation under challenging severe accident conditions in order to further enhance the assessment of hydrogen mitigation efficiency. Complementary test series in the REKO and THAI facilities provide comprehensive databases for understanding PAR behavior and model development. 9
10 REKO platform 10 Set of facilities at different scales (flow tubes 5.5 m³ vessel) Investigations from single catalyst elements to full recombiners Well defined boundary conditions for numerical model development Research goals: Reliable simulation of PAR operation under severe accident conditions Contribution to PAR implementation strategy and performance assessment Testing of enhanced materials and concepts Increasing usage of German expertise
11 REKO results: Understanding PAR operation Experimental studies and projects have been performed since more than 20 years REKO data base has served for PAR model development and validation worldwide Specific insights into hydrogen conversion under challenging conditions Presence of carbon monoxide Oxygen-lean conditions Ignition on hot catalyst surfaces Impact of cable fire products Impact of adverse flow conditions (counter-current flow) Support of international PAR and catalyst development Qualification tests of commercial non-nuclear PARs 11
12 THAI results: PAR performance Tests using commercially available PAR units from vendors AREVA, AECL (now CNL), NIS About 50 PAR tests conducted so far in THAI Objectives of the THAI PAR tests PAR performance behaviour: f (pressure, temperature, H 2 concentration, steam concentration) PAR performance under O 2 -lean atmosphere (reduced recombination rate) PAR poisoning by fission products (soluble/insoluble aerosol mixture, iodine) Thermal decomposition of CsI to gaseous I 2 Conditions for ignition induced by PAR PAR performance under counter-current flow AREVA PAR installed in THAI vessel 12 Effect of CO on PAR performance/ignition (planned)
13 Iodine and aerosol behavior Iodine and aerosol issues are of high relevance with regard to severe accidents and beyond design-basis accidents and potential consequences in terms of land contaminations. In order to prevent long-term consequences for the environment and population as a result of severe accidents, filtered containment venting systems (FCVS) are installed in several nuclear power plants, mainly in Europe. The early source term is dominated by iodine-131 (no full retention of organic iodine within FCVS). One of the most relevant processes being conductive to source term mitigation is pool scrubbing, the particle retention in water pools. 13
14 THAI results: Iodine and fission product behaviour Reduction of gaseous iodine inventory by adsorption on dry/wet painted surfaces and on aerosol particles Transport & distribution of reactive gaseous iodine in a multi-compartment system with inhomogeneous thermal-hydraulic conditions Pool scrubbing tests are currently under progress Re-entrainment of non-volatile fission products and gaseous iodine from boiling water pool 14
15 SAAB facility 15 Investigation of particle retention in a water pool with variable height between m Aerosols: SnO 2, CsI, CsOH, Cs 2 MoO 4, Ag Test parameters: Pool height Gas composition (air, steam, N 2, He) Injection velocity and cross section (Re ~ ) Particle diameter/ size distribution Particle concentration Injection direction Bubble monitoring by means of high speed camera
16 16 SAAB results: Pool scrubbing characteristics Research objectives Providing a database to validate and enhance pool scrubbing models Development of a correlation based on different parameters (replacing very detailed but nontransparent modeling like SPARC-B, SUPRA or BUSCA) In-house development of aerosol generators for long-term injection with const. particle characteristics Successful plausibility check of the measurement concept First test series and correlation development on-going
17 Outlook OECD/NEA THAI-3 project (on-going) LWR issues under severe accident conditions related to fission product behavior, PARs and flame propagation Fission product release from hot water pool involving pool scrubbing related phenomena and resuspension of pre-deposited fission products by hydrogen deflagration ( delayed source term ) SAAB II project Particle retention in a water pool (single effects and validation) with insoluble, soluble and mixed aerosols Effect of cable fire aerosols on PAR operation SETCOM program (on-going) Wall condensation under mixed convection conditions 17
18 Acknowledgments The German Federal Ministry for Economic Affairs and Energy (BMWi) supports financially the THAI, SETCOM, SAAB and H2REKO research programs. The sponsorship by the countries of the OECD/NEA THAI-1, THAI-2 and THAI-3 project partners is gratefully acknowledged. 18
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