| 1. |
- Bandini, G., et al.
(författare)
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Assessment of systems codes and their coupling with CFD codes in thermal-hydraulic applications to innovative reactors
- 2015
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Ingår i: Nuclear Engineering and Design. - : Elsevier BV. - 0029-5493 .- 1872-759X. ; 281, s. 22-38
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Tidskriftsartikel (refereegranskat)abstract
- The THINS project of the 7th Framework EU Program on nuclear fission safety is devoted to the investigation of crosscutting thermal hydraulic issues for innovative nuclear systems. A significant effort in the project has been dedicated to the qualification and validation of system codes currently employed in thermal hydraulic transient analysis for nuclear reactors. This assessment is based either on already available experimental data, or on the data provided by test campaigns carried out in the frame of THINS project activities. Data provided by TALL and CIRCE facilities were used in the assessment of system codes for HLM reactors, while the PHENIX ultimate natural circulation test was used as reference for a benchmark exercise among system codes for sodium-cooled reactor applications. In addition, a promising grid-free pool model based on proper orthogonal decomposition is proposed to overcome the limits shown by the thermal hydraulic system codes in the simulation of pool-type systems. Furthermore, multi-scale system-CFD solutions have been developed and validated for innovative nuclear system applications. For this purpose, data from the PHENIX experiments have been used, and data are provided by the tests conducted with new configuration of the TALL-3D facility, which accommodates a 3D test section within the primary circuit. The TALL-3D measurements are currently used for the validation of the coupling between system and CFD codes.
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| 2. |
- Cheng, X., et al.
(författare)
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European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems
- 2015
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Ingår i: Nuclear Engineering and Design. - : Elsevier BV. - 0029-5493 .- 1872-759X. ; 290, s. 2-12
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Tidskriftsartikel (refereegranskat)abstract
- Thermal-hydraulics is recognized as a key scientific subject in the development of innovative reactor systems. In Europe, a consortium is established consisting of 24 institutions of universities, research centers and nuclear industries with the main objectives to identify and to perform research activities on important crosscutting thermal-hydraulic issues encountered in various innovative nuclear systems. For this purpose the large-scale integrated research project THINS (Thermal-Hydraulics of Innovative Nuclear Systems) is launched in the 7th Framework Programme FP7 of European Union. The main topics considered in the THINS project are (a) advanced reactor core thermal-hydraulics, (b) single phase mixed convection, (c) single phase turbulence, (d) multiphase flow, and (e) numerical code coupling and qualification. The main objectives of the project are: Generation of a data base for the development and validation of new models and codes describing the selected crosscutting thermal-hydraulic phenomena. Development of new physical models and modeling approaches for more accurate description of the crosscutting thermal-hydraulic phenomena. Improvement of the numerical engineering tools for the design analysis of the innovative nuclear systems. This paper describes the technical tasks and methodologies applied to achieve the objectives. Main results achieved so far are summarized. This paper serves also as a guidance of this special issue.
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| 3. |
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| 4. |
- Papukchiev, A., et al.
(författare)
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Importance of conjugate heat transfer modeling in transient CFD simulations
- 2019
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Ingår i: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. - : American Nuclear Society. ; , s. 615-626
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Konferensbidrag (refereegranskat)abstract
- Within the European SESAME project, system thermal-hydraulics (STH), computational fluid dynamics (CFD) and coupled 1D-3D thermal-hydraulic simulations are being carried out for Generation IV nuclear systems. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH participated in the project with activities related to the development and validation of CFD and coupled CFD-STH codes. The TALL-3D facility, operated by the KTH Royal Institute of Technology in Stockholm, is designed for thermal-hydraulic experiments with lead-bismuth eutectic (LBE) coolant. A well-instrumented, partially heated test section with cylindrical form is installed in the primary circuit. It is the domain of complex 3D flow and heat transfer phenomena. The CFD analyses showed that only the consideration of the fluid domain is not sufficient for correct prediction of the thermal-hydraulic transient dynamics. Therefore, solid structures like test section walls, inner circular plate, test section heater and even the insulation were explicitly included in the CFD model. This allowed the consideration in the simulations of the heat conduction and the thermal inertia of these components. The paper focuses on the analysis of the observed thermal-hydraulic flow phenomena during the TG03.S301.04 experiment and the comparison between ANSYS CFX predictions and data. Moreover, the influence of conjugate heat transfer (CHT) on the numerical results is investigated and discussed.
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| 5. |
- Papukchiev, A., et al.
(författare)
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Multiscale analysis of forced and natural convection including heat transfer phenomena in the tall-3D experimental facility
- 2015
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Ingår i: International Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015. - : American Nuclear Society. - 9781510811843 ; , s. 2917-2930
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Konferensbidrag (refereegranskat)abstract
- Within the European FP7 project THINS (Thermal Hydraulics of Innovative Nuclear Systems), numerical tools for the simulation of the thermal-hydraulics of next generation rector systems were developed, applied and validated for innovative coolants. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, the Technische Universitaet Muenchen (TUM) and the Royal Institute of Technology (KTH) participated in THINS activities related to the development and validation of computational fluid dynamics (CFD), System Thermal Hydraulics (STH) and coupled STH - CFD codes. High quality measurements from the experiments performed at the TALL-3D facility, operated by KTH, were used to assess the numerical results. This paper summarizes the work accomplished for the validation of the coupled codes ATHLET-ANSYS CFX and RELAP5/STAR CCM+ and highlights the main results achieved for the T01.09 experiment.
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| 6. |
- Papukchiev, A., et al.
(författare)
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Validation of the system thermal-hydraulics code ATHlet for the simulation of transient lead-bismuth eutectic flows
- 2019
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Ingår i: 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. - : American Nuclear Society. ; , s. 810-822
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Konferensbidrag (refereegranskat)abstract
- Within the European SESAME project, system thermal-hydraulics (STH), computational fluid dynamics (CFD) and coupled 1D-3D thermal-hydraulic simulations were carried out for Generation IV nuclear systems. The Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH participated in the project with activities related to the development and validation of CFD and coupled CFD-STH codes. The TALL-3D facility, operated by the KTH Royal Institute of Technology in Stockholm, is designed for thermal-hydraulic experiments with lead-bismuth eutectic (LBE) coolant. A well-instrumented, partially heated test section with cylindrical form is installed in the primary circuit, which is domain of complex 3D flow and heat transfer phenomena. Three different experiments were calculated within a benchmark, organized by KTH: two with coupled programs and one with STH stand-alone code. This paper focuses on the analysis of the observed thermal-hydraulic flow phenomena during the TG03.S310.01 experiment and the comparison between ATHLET predictions and data.
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