Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment
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Zhi Yang
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Joachim Herb
Abstract
System thermal-hydraulics (STH) codes are successfully used in the last decades for design and analysis of the physical behavior of nuclear power plants (NPPs). These programs provide reliable results at comparatively low computational cost, but have limited capabilities to predict complex 3D flow phenomena, which is possible with Computational Fluid Dynamics (CFD) tools. In order to combine the advantages of STH and CFD codes, algorithms to couple these are developed. At GRS, a new OpenFOAM solver, based on the volume of fluid (VOF) method, was developed together with new coupling boundary conditions to couple the CFD program OpenFOAM with the system code ATHLET. In a next step, verification and validation activities were carried out. These included the analysis of a Pressurized Thermal Shock (PTS) scenario. For this purpose, data from the OECD/NEA ROSA V Test 1.1, carried out in the Japanese Large-Scale Test Facility (LSTF) was used. The experiment investigated the temperature stratification after emergency core cooling (ECC) injection under single- and two-phase natural circulation conditions in the primary cooling circuit of a pressurized water reactor (PWR). This paper discusses the results of the coupled simulations, compares the numerical results with experimental data, and identifies areas for future improvements.
Funding source: German Federal Ministry of the Environment, Nature Conservation, Nuclear Safety and Consumer Protection
Award Identifier / Grant number: RS1591 (WEVAFOAM)
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Research ethics: Not applicable.
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Author contributions: The authors have accepted responsibility for the entire content of this manuscript and approved its submission.
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Competing interests: The authors state no conflict of interest.
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Research Funding: This work has been funded by the German Federal Ministry of the Environment, Nature Conservation, Nuclear Safety and Consumer Protection within reactor safety research project RS1591 (WEVAFOAM).
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Data availability: Not applicable.
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© 2024 Walter de Gruyter GmbH, Berlin/Boston
Articles in the same Issue
- Frontmatter
- The 34th German CFD network of competence meeting: numerical 3D simulation of reactor primary cooling circuit and containment flows
- The European GO-VIKING project on flow-induced vibrations: overview and current status
- CFD simulation on droplet behaviour in post-dryout region
- Coupled AC2-CFD simulations for a high-pressure core melt accident scenario
- Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment
- CFD modelling of flashing flows for nuclear safety analysis: possibilities and challenges
- Implementation of the preCICE coupling interface for AC2/ATHLET
- Large-scale PANDA facility – radiation experiments and CFD calculations
- Overview on GRS CFD activities related to containment applications
- Calendar of events
Articles in the same Issue
- Frontmatter
- The 34th German CFD network of competence meeting: numerical 3D simulation of reactor primary cooling circuit and containment flows
- The European GO-VIKING project on flow-induced vibrations: overview and current status
- CFD simulation on droplet behaviour in post-dryout region
- Coupled AC2-CFD simulations for a high-pressure core melt accident scenario
- Validation of coupled ATHLET-OpenFOAM simulation on a large-scale single- and two-phase flow experiment
- CFD modelling of flashing flows for nuclear safety analysis: possibilities and challenges
- Implementation of the preCICE coupling interface for AC2/ATHLET
- Large-scale PANDA facility – radiation experiments and CFD calculations
- Overview on GRS CFD activities related to containment applications
- Calendar of events
