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Paranjape, S., Kapulla, R., Kudinov, P., Chae, M. S. & Paladino, D. (2024). Experimental results of thermocline evolution in a water pool under combined effect of steam venting and water injection. Nuclear Engineering and Design, 419, Article ID 112914.
Open this publication in new window or tab >>Experimental results of thermocline evolution in a water pool under combined effect of steam venting and water injection
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2024 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 419, article id 112914Article in journal (Refereed) Published
Abstract [en]

In this article we present the results of six experiments identified as HP5 series, performed in the large-scale PANDA (Passive Nachzerfallswärmeabfuhr und Druck-Abbau Testanlage) thermal-hydraulics facility within the OECD/NEA HYMERES (Hydrogen Mitigation Experiments for Reactor Safety) project. These experiments focus on thermal stratification and mixing induced by steam injection in a water pool through a vertical sparger with horizontal holes. The pool stratification was created at low steam flow rate and mixing was achieved by either: steam injection at higher flow rate or a combined effect of injection low steam flow rate and horizontal water jet. The phenomena investigated are relevant for the safety of light water reactor, normal operation and accident scenarios during which steam is directly vented and condensed in a large water pool. We find that the initial pool temperature plays an important role in the thermocline formation. Higher initial pool temperature leads to the formation of a thermocline at lower elevations farther away from the sparger and with a larger density difference across the thermocline. The flow field in the pool is affected by initial pool temperature as indicated by Particle Image Velocimetry (PIV). Higher steam flow rate during the second phase showed the effect of steam momentum on mixing. It was found that for the range of parameters considered in the experiments with water injection the density difference between the pool water and the water injected by the nozzle has a greater influence on the mixing time compared with the momentum of the water jet.

Place, publisher, year, edition, pages
Elsevier BV, 2024
Keywords
PANDA facility, PIV, Sparger, Suppression pool, Thermocline
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-343191 (URN)10.1016/j.nucengdes.2024.112914 (DOI)2-s2.0-85183585049 (Scopus ID)
Note

QC 20240209

Available from: 2024-02-08 Created: 2024-02-08 Last updated: 2024-02-09Bibliographically approved
Wong, K. W., Mickus, I., Torkelson, N., Vasudevan, S., Li, H., Grishchenko, D. & Kudinov, P. (2024). Hydrodynamic design of the Separate Effect test facility for Flow-Accelerated Corrosion and Erosion (SEFACE) studies in liquid lead. Nuclear Engineering and Design, 417, Article ID 112852.
Open this publication in new window or tab >>Hydrodynamic design of the Separate Effect test facility for Flow-Accelerated Corrosion and Erosion (SEFACE) studies in liquid lead
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2024 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 417, article id 112852Article in journal (Refereed) Published
Abstract [en]

Flow-accelerated corrosion and erosion (FACE) phenomena can be crucial for performance of structural elements in heavy liquid metal (HLM) cooled reactor systems. Existing experimental observations indicate that turbulent flow characteristic can affect FACE, but there is no quantitative data that can be used for model development and validation. Main recirculation pump impellers, which operate at high relative velocities and rotational flow conditions can be especially vulnerable to FACE. For comparison, the core internals operate at lower velocities and in axial flow conditions, but at higher temperatures and neutron fluence. Hence, systematic experimental data is needed to improve our knowledge on FACE phenomena. The Separate Effect Test Facility for Flow-Accelerated Corrosion and Erosion (SEFACE) is designed to obtain such experimental data including high relative velocities (up 20 ms−1) and high temperatures (400 to 550 °C) of liquid lead. This article focuses on the hydrodynamic design of SEFACE. The aim of the design is to achieve well defined flow conditions for experiments and ensure safe operation of the facility. First, we examine three design concepts (i.e., forced convection loop, rotating cylinder, and rotating disk) and motivate the choice of the rotating disk approach for SEFACE. Second, we discuss different design options, i.e., a confined rotor–stator test chamber and the unconfined rotating disk configuration. We used Reynolds-Averaged Navier Stokes (RANS) calculations to identify and solve the issues stemming from the high rotational speed. These include, for instance, lead free surface deformation, radial pressure buildup, and axial bending forces due to asymmetric test chamber. The CFD-derived torque and power predictions in rotor–stator and rotating disk systems are verified with selected empirical turbulent friction factor correlations or/and DNS calculations. We demonstrate that the developed hydrodynamic design of SEFACE solves identified issues and enables obtaining experimental data under well-defined flow conditions. The findings are deemed to also be applicable to the design of rotating disk-type FACE installations for other liquid mediums.

Place, publisher, year, edition, pages
Elsevier BV, 2024
National Category
Fluid Mechanics and Acoustics
Identifiers
urn:nbn:se:kth:diva-341938 (URN)10.1016/j.nucengdes.2023.112852 (DOI)2-s2.0-85180415014 (Scopus ID)
Note

QC 20240108

Available from: 2024-01-08 Created: 2024-01-08 Last updated: 2024-01-08Bibliographically approved
Wong, K. W., Mickus, I., Vasudevan, S., Li, H., Grishchenko, D. & Kudinov, P. (2023). CFD STUDIES OF SEPARATE EFFECT FLOW ACCELERATED CORROSION AND EROSION (SEFACE) FACILITY FOR HEAVY LIQUID METAL. In: Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023. Paper presented at 30th International Conference on Nuclear Engineering, ICONE 2023, Kyoto, Japan, May 21 2023 - May 26 2023. American Society of Mechanical Engineers (ASME)
Open this publication in new window or tab >>CFD STUDIES OF SEPARATE EFFECT FLOW ACCELERATED CORROSION AND EROSION (SEFACE) FACILITY FOR HEAVY LIQUID METAL
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2023 (English)In: Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023, American Society of Mechanical Engineers (ASME) , 2023Conference paper, Published paper (Refereed)
Abstract [en]

Long-term material compatibility in heavy liquid metal (HLM) remains a challenge for the successful deployment of HLM-based technologies. Flow-accelerated corrosion and erosion (FACE) phenomena can lead to continual material deterioration, which needs to be considered throughout the reactor design stage. Nonetheless, known experimental data are inadequate to cover all the prototypical flow regimes during LFR's operation. Modelling of the FAC/FACE phenomena remains mostly in lumped parameter/subchannel scales, where the FAC model is coupled to the bulk flow of the pipe or subchannel. These methodologies might produce a sufficient prediction for the core internals; however, this might not be suitable for the pump impeller due to comparatively greater relative velocity and the occurrence of transient flow patterns near the rotating impeller. To establish an understanding of the connection between turbulence and FACE, the liquid lead-based Separate Effect Flow Accelerated Corrosion and Erosion (SEFACE) facility is currently under design at KTH in the framework of the Sustainable Nuclear Energy Research In Sweden (SUNRISE) project. SEFACE attempts to investigate FACE phenomena in the liquid lead and produce quantifiable validation data for model development. The paper divides itself into two parts. Part I refers to the study of operational conditions in SEFACE via Reynolds Averaged Navier Stokes (RANS) simulation, while Part II deals with the recent attempt on modelling time-dependent flow shear on rotating disks based on large eddy simulation (LES). The paper begins with a brief review of prior studies on flow-accelerated corrosion. Following that, the SEFACE facility's design concept is laid out considering several physical and operational constraints. A periodic wedge of the SEFACE test chamber is chosen to examine the facility's time-averaged behaviour. The k-ω shear stress transport (SST) model was employed for the simulations. The torque prediction on the rotating disk system is verified with the empirical frictional factor prediction. The latest hydrodynamic design enables SEFACE to be spun at 1200 revolutions per minute (corresponding to a maximum velocity of 21 m/s) without causing free surface deformation or excessive pressure. SEFACE permits the collecting of experimental data under the effect of various relative velocities in a single experiment round. The second part of the paper focuses on a recent attempt to determine the wall shear stress distribution on a rotating disk using wall-modelled large eddy simulation (WMLES S-Omega). The obtained amplitude and frequency of wall shear stress fluctuations will aid model development in future.

Place, publisher, year, edition, pages
American Society of Mechanical Engineers (ASME), 2023
Keywords
Flow Accelerated Corrosion and Erosion (FACE), Liquid Lead, SEFACE, SUNRISE
National Category
Fluid Mechanics and Acoustics Energy Engineering
Identifiers
urn:nbn:se:kth:diva-340800 (URN)2-s2.0-85178511938 (Scopus ID)
Conference
30th International Conference on Nuclear Engineering, ICONE 2023, Kyoto, Japan, May 21 2023 - May 26 2023
Note

Part of ISBN 9784888982566

QC 20231214

Available from: 2023-12-14 Created: 2023-12-14 Last updated: 2024-03-18Bibliographically approved
Wang, X., Grishchenko, D. & Kudinov, P. (2023). Simulation of jets induced by steam injection through multi-hole sparger using effective heat and momentum models. Nuclear Engineering and Design, 405, Article ID 112222.
Open this publication in new window or tab >>Simulation of jets induced by steam injection through multi-hole sparger using effective heat and momentum models
2023 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 405, article id 112222Article in journal (Refereed) Published
Abstract [en]

Direct contact condensation (DCC) of steam in the pressure suppression pool (PSP) is used to control containment pressure in Boiling Water Reactors (BWRs) and Advanced Pressurized Water Reactors (APWRs). The competition between momentum and heat sources induced by steam injection through multi-hole spargers and blowdown pipes determines whether the pool is thermally stratified or mixed. Development of thermal stratification affects capacity of the PSP to condense steam. To enable computationally efficient modeling of the PSP transients, the Effective Heat Source (EHS) and Effective Momentum Source (EMS) models have been proposed previously. The EHS/EMS models enable simulation of the large scale pool behavior without explicit modeling of the steam water interface and DCC phenomena. One of the problems for an optimal implementation of the EHS/EMS models is the definition of the boundary conditions that impose distribution of the momentum and heat sources. In this work, EHS/EMS models are implemented using “Unit Cell” approach in ANSYS Fluent to provide detailed numerical analysis of the individual turbulent jets induced by steam injection through the sparger holes. The model is validated against data from Particle Image Velocimetry (PIV) and temperature measurements for a range of steam injection conditions in the PANDA HP5 tests. Good agreement between the test data and simulations suggests that the proposed model can provide sufficiently accurate prediction of both local and large scale phenomena induced by steam injection into the pool.

Place, publisher, year, edition, pages
Elsevier BV, 2023
Keywords
Direct contact condensation, EHS/EMS models, Multi-hole sparger, PIV, Turbulent jet
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-331100 (URN)10.1016/j.nucengdes.2023.112222 (DOI)000948824000001 ()2-s2.0-85149919131 (Scopus ID)
Note

QC 20230705

Available from: 2023-07-05 Created: 2023-07-05 Last updated: 2023-07-05Bibliographically approved
Wang, X., Acharya, G., Grishchenko, D. & Kudinov, P. (2023). TRANSIENT ANALYSIS OF THERMAL STRATIFICATION AND MIXING IN PRESSURE SUPPRESSION POOL DURING ANTICIPATED SCENARIOS. In: Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023: . Paper presented at 30th International Conference on Nuclear Engineering, ICONE 2023, Kyoto, Japan, May 21 2023 - May 26 2023. American Society of Mechanical Engineers (ASME)
Open this publication in new window or tab >>TRANSIENT ANALYSIS OF THERMAL STRATIFICATION AND MIXING IN PRESSURE SUPPRESSION POOL DURING ANTICIPATED SCENARIOS
2023 (English)In: Proceedings of the 30th International Conference on Nuclear Engineering "Nuclear, Thermal, and Renewables: United to Provide Carbon Neutral Power", ICONE 2023, American Society of Mechanical Engineers (ASME) , 2023Conference paper, Published paper (Refereed)
Abstract [en]

Steam discharging through spargers and blowdown pipes into the Pressure Suppression Pool (PSP) is employed in Boiling Water Reactor (BWR) to prevent overpressure of the reactor vessel and containment. The capability of suppression can be reduced during the operation when the thermal stratification is developed. Direct modeling of steam injection into a water pool with long-term transient is computationally expensive due to the large-scale difference in space and time. To enable such prediction, Effective Heat source and Effective Momentum source (EHS/EMS) models are proposed. In previous work, we demonstrated the implantation of EHS/EMS models in the Computational Fluid Dynamics (CFD) tool and its application to plant simulation. In this work, we use the developed model to further investigate the thermal stratification and mixing in the PSP of a Nordic BWR. The event to be analyzed is initiated by spurious activation of one valve in the safety injection system. The focus of the simulations is to investigate the possibility of stratification development and understand the effects of the activation of different systems on pool behavior. Pool transient is simulated by CFD code (ANSYS Fluent) with EHS/EMS models and the injection conditions of the steam are derived from the simulation results performed by the system-level codes (GOTHIC).

Place, publisher, year, edition, pages
American Society of Mechanical Engineers (ASME), 2023
Keywords
CFD, EHS/EMS models, Pressure suppression pool, sparger, steam condensation, thermal stratification
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-341468 (URN)2-s2.0-85178236963 (Scopus ID)
Conference
30th International Conference on Nuclear Engineering, ICONE 2023, Kyoto, Japan, May 21 2023 - May 26 2023
Note

QC 20240109

Part of ISBN 9784888982566

Available from: 2024-01-09 Created: 2024-01-09 Last updated: 2024-01-09Bibliographically approved
Hernandez, C. R., Grishchenko, D., Kudinov, P., Wallenius, J. & Luxat, J. (2022). Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor. Nuclear Engineering and Design, 392, 111773, Article ID 111773.
Open this publication in new window or tab >>Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor
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2022 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 392, p. 111773-, article id 111773Article in journal (Refereed) Published
Abstract [en]

With the deployment of advanced and small modular reactors (SMRs), it is important to develop the tools to assess their safety. This work presents the different components of a CFD based model for simulating transients in a pool-type small lead cooled reactor. The model encompasses the entire primary circuit with a simplification of the fuel channels, pumps and steam generators. Those parts are modelled through heat and momentum sources (or sinks), similar to the porous medium used in other studies. The CFD solver is coupled with a finite volume solver for fuel pin temperature and a point kinetics solver for neutronics. Free surface is modelled in CFD with multiphase volume of fluid method. The set of methods that is used in this work constitute a novelty for modelling lead cooled reactors. The goal is to have a model that is relatively simple to implement in order to study the effect of some parameters on reactor transients like an unprotected loss of flow. The focus of this study is to describe in detail every individual component of the model, namely the fuel channels, fuel pin temperature, neutronics, coupling strategy, pump and steam generators. In addition, CFD simulations are compared against experimental data from the TALL-3D facility. The purpose of this comparison is to verify that the models and parameters of the CFD software (STAR-CCM+) are capable of reproducing a flow of heavy metal. A future publication will provide the simulation results of an integrated model with all the components.

Place, publisher, year, edition, pages
Elsevier BV, 2022
Keywords
Heavy-metal reactors, SMR, CFD, Transients
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-314847 (URN)10.1016/j.nucengdes.2022.111773 (DOI)000807473000002 ()2-s2.0-85128309959 (Scopus ID)
Note

QC 20220627

Available from: 2022-06-27 Created: 2022-06-27 Last updated: 2022-06-27Bibliographically approved
Thakre, S., Konovalenko, A., Ahlin, A. & Kudinov, P. (2022). Experimental investigation of solid particle spreading driven by gas injection into a pool of water. Annals of Nuclear Energy, 174, 109165-109165, Article ID 109165.
Open this publication in new window or tab >>Experimental investigation of solid particle spreading driven by gas injection into a pool of water
2022 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 174, p. 109165-109165, article id 109165Article in journal (Refereed) Published
Abstract [en]

Motivated from the fuel–coolant interaction phenomena in boiling water reactors, in the present work, effect of natural convection flows, set during the melt dripping, on the nature of formation of debris bed, of solidified particles, at the bottom floor is studied. Standard shape solid particles are used to simulate the dripping melt and their paths are tracked using a particle tracking technique to acquire additional data such as particles velocity, travel time and path. The experimental studies performed on PDS-P facility are designed to study the separate effects and generate the data for codes validation. A novel particle tracking technique allowed quantification of kinetic properties for every particle. The results helped in refinement of the particles distribution on the floor, quantifying the debris bed shape. Higher pool depths and natural convection flows rates are seen effective in enhancing the distribution of debris particles, creating shallow and well spread debris bed.

Place, publisher, year, edition, pages
Elsevier BV, 2022
National Category
Fluid Mechanics and Acoustics Other Physics Topics
Research subject
Physics, Nuclear Engineering
Identifiers
urn:nbn:se:kth:diva-312742 (URN)10.1016/j.anucene.2022.109165 (DOI)000803675700012 ()2-s2.0-85129540594 (Scopus ID)
Note

QC 20220523

Available from: 2022-05-22 Created: 2022-05-22 Last updated: 2022-06-25Bibliographically approved
Wang, X., Grishchenko, D. & Kudinov, P. (2022). Pre-test analysis for definition of steam injection tests through multi-hole sparger in PANDA facility. Nuclear Engineering and Design, 386, Article ID 111573.
Open this publication in new window or tab >>Pre-test analysis for definition of steam injection tests through multi-hole sparger in PANDA facility
2022 (English)In: Nuclear Engineering and Design, ISSN 0029-5493, E-ISSN 1872-759X, Vol. 386, article id 111573Article in journal (Refereed) Published
Abstract [en]

Pressure Suppression Pool (PSP) is a passive safety feature in Boiling Water Reactors (BWR) and Advanced Pressurized (AP) reactors. Steam released from the primary coolant system is condensed in a large water pool to prevent containment overpressure. Injected steam induces sources of heat (buoyancy force) and momentum (inertia). The competition between the sources might result in the development of thermal stratification or mixing of the pool. Increased temperature of the top pool layer leads to higher partial pressure of steam in the containment and thus reduces pressure suppression capacity of the pool. Models with predictive capabilities are needed for the analysis of the reactor pool transients. Development and validation of the models require adequate experimental data. In this work we discuss results of the pre-test analysis that was carried out to select conditions for the tests with steam injection through sparger head and Load Reduction Ring (LRR) in a large scale PANDA facility. The aim of the tests was to obtain data on pool thermal stratification and mixing under different regimes of steam injection. Effective Heat Source (EHS) and Effective Momentum Source (EMS) models were implemented in a computational fluid dynamics (CFD) code in order to carry out the analysis. Evolution of the pool temperature and velocity characteristics were analyzed in the scoping analysis to provide suggestions for selection of (i) pool depth, (ii) elevations of the sparger head and LRR, (iii) number of open LRR holes, (iv) layout of instrumentation, and (v) steam injection procedure for each test.

Place, publisher, year, edition, pages
Elsevier BV, 2022
Keywords
Sparger, Steam condensation, Pressure suppression pool, CFD, EHS, EMS models
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-311621 (URN)10.1016/j.nucengdes.2021.111573 (DOI)000782282800005 ()2-s2.0-85120684231 (Scopus ID)
Note

QC 20220530

Available from: 2022-05-02 Created: 2022-05-02 Last updated: 2022-06-25Bibliographically approved
Galushin, S., Marklund, A. R., Olsson, A., Bäckström, O., Grishchenko, D. & Kudinov, P. (2022). Treatment of Phenomenological Uncertainties in Level 2 PSA for Nordic BWR Using Risk Oriented Accident Analysis Methodology. In: Probabilistic Safety Assessment and Management, PSAM 2022: . Paper presented at 16th International Conference on Probabilistic Safety Assessment and Management, PSAM 2022, Honolulu, United States of America, Jun 26 2022 - Jul 1 2022. International Association for Probablistic Safety Assessment and Management (IAPSAM)
Open this publication in new window or tab >>Treatment of Phenomenological Uncertainties in Level 2 PSA for Nordic BWR Using Risk Oriented Accident Analysis Methodology
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2022 (English)In: Probabilistic Safety Assessment and Management, PSAM 2022, International Association for Probablistic Safety Assessment and Management (IAPSAM) , 2022Conference paper, Published paper (Refereed)
Abstract [en]

A comprehensive and robust assessment of phenomenological uncertainties is a challenge for the current real-life PSA L2 applications, since such uncertainty is majorly driven by physical phenomena and timing of events. Typically, the static PSA models are built on a pre-determined set of scenario parameters to describe the accident progression sequence and use a limited number of simulations in the underlying deterministic analysis to evaluate the consequences. The Risk Oriented Accident Analysis Methodology (ROAAM+) has been developed to enable consistent and comprehensive treatment of both epistemic and aleatory sources of uncertainty in risk quantification. The framework is comprised of a set of deterministic models that simulate different stages of the accident progression, and a probabilistic platform that performs quantification of the uncertainty in conditional containment failure probability. This information is used for enhanced modeling in the PSA-L2 for improved definition of sequences, where information from the ROAAM is used to refine PSA model resolution regarding risk important accident scenario parameters, that can be modelled within the PSA. This work presents an example of application of the dynamic approach in a large-scale PSA model and demonstrate the integration of the ROAAM+ results in the PSA model.

Place, publisher, year, edition, pages
International Association for Probablistic Safety Assessment and Management (IAPSAM), 2022
National Category
Reliability and Maintenance Energy Engineering Probability Theory and Statistics
Identifiers
urn:nbn:se:kth:diva-333460 (URN)2-s2.0-85146257554 (Scopus ID)
Conference
16th International Conference on Probabilistic Safety Assessment and Management, PSAM 2022, Honolulu, United States of America, Jun 26 2022 - Jul 1 2022
Note

QC 20230802

Available from: 2023-08-02 Created: 2023-08-02 Last updated: 2023-08-02Bibliographically approved
Wang, X., Grishchenko, D. & Kudinov, P. (2021). Development of effective momentum model for steam injection through multi-hole spargers: Unit cell model. In: Proceedings of 2021 28th International Conference on Nuclear Engineering (ICONE28): . Paper presented at 28th ASME International Conference on Nuclear Engineering (ICONE) - Nuclear Energy the Future Zero Carbon Power, AUG 04-06, 2021, ELECTR NETWORK. ASME International
Open this publication in new window or tab >>Development of effective momentum model for steam injection through multi-hole spargers: Unit cell model
2021 (English)In: Proceedings of 2021 28th International Conference on Nuclear Engineering (ICONE28), ASME International , 2021Conference paper, Published paper (Refereed)
Abstract [en]

The Steam injection through multi-hole spargers into the pressure suppression pool (PSP) is used in light water reactors to prevent containment over-pressure. The development of thermal stratification in the PSP can reduce its cooling capacity and results in higher containment pressures compared to completely mixed pool conditions. Explicit modelling of direct contact condensation (DCC) of steam at the steam-water interface is a challenge for contemporary codes. Effective Heat Source (EHS) and Effective Momentum Source (EMS) models have been proposed to enable the prediction of thermal stratification and mixing transients induced by steam condensation in a large pool. The general idea of the EHS/EMS is to resolve the effect of the DCC phenomena on a large pool, instead of explicit modelling of the small-scale phenomena at steam-water interface. The EHS/EMS models can be implemented using (i) respective boundary conditions at the boundary of the Steam Condensation Region (SCR) or (ii) using source terms in the heat and momentum transport equations. In previous work, EHS/EMS models were implemented using the second approach and validated against data from PPOOLEX and PANDA tests. It was found that results are sensitive to the spatial distribution of the source terms. Since the current data are not sufficient to provide a reasonable distribution, a preliminary study of the first method was done in this paper. The goal of this work is to develop a 'Unit Cell' model by using respective boundary conditions for steam injection through multi-hole sparger. The condensed turbulent jet is resolved by introducing the liquid jet with the same effective momentum and heat as the injected steam. A uniform velocity profile solved by EMS model and the temperature boundary solved by EHS model is provided on each injection hole of the sparger wall. Validation is conducted against sparger test in PANDA facilities.

Place, publisher, year, edition, pages
ASME International, 2021
Keywords
Condensed turbulent jet, Direct contact condensation, EHS/EMS models, Sparger, Thermal stratification, Boundary conditions, Condensation, Lakes, Light water reactors, Momentum, Steam, Steam condensers, Effective heat source/effective momentum source model, Heat sources, Momentum sources, Multi holes, Source models, Sparge, Steam injection, Turbulent jet
National Category
Energy Engineering
Identifiers
urn:nbn:se:kth:diva-312337 (URN)10.1115/ICONE28-65751 (DOI)000885885500084 ()2-s2.0-85117733394 (Scopus ID)
Conference
28th ASME International Conference on Nuclear Engineering (ICONE) - Nuclear Energy the Future Zero Carbon Power, AUG 04-06, 2021, ELECTR NETWORK
Note

Part of proceedings: ISBN 978-0-7918-8527-7

QC 20220530

Available from: 2022-05-30 Created: 2022-05-30 Last updated: 2022-12-15Bibliographically approved
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Identifiers
ORCID iD: ORCID iD iconorcid.org/0000-0002-0683-9136

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