Abstract
The sloshing in a confined tank is essential to evaluate the safety function of floating plants, e.g., offshore floating nuclear power plants (OFNPs). The transient plant behavior has been simulated with nuclear system analysis codes. In turn, the sloshing motion has been simulated with computational fluid dynamics (CFD) codes. Although some system codes can calculate three-dimensional flow, the available features were limited, exceptionally dynamic phasic behaviors, including the sloshing motions. The paper addresses the time-dependent acceleration as body force in the momentum equation of the system code TRACE and the validation of the pressure impact acting on the wall and fixed-roof of the cylindrical tank. The modified TRACE code was validated against the sloshing experiment. In addition, the TRACE code results were compared with CFD code (Star-CCM+) results. Two different methods were compared: the volume of fluid (VOF) method and the two-fluid flow method, namely the Eulerian multiphase model (EMP). The results of the flow models indicate that the free-surface VOF model agrees with the experimental results. However, the fast transient motions are suppressed for the two-flow model in the CFD and TRACE code.
Original language | English |
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Journal | International Conference on Thermal Engineering |
Volume | 1 |
Issue number | 1 |
Publication status | Published - 2024 |
Event | 15th International Conference on Thermal Engineering: Theory and Applications, ICTEA 2024 - Tashkent, Uzbekistan Duration: 2024 May 28 → 2024 Jun 1 |
Keywords
- CFD
- Sloshing
- System analysis code
- TRACE
- Two-fluid model
- Volume of fluid
ASJC Scopus subject areas
- Energy (miscellaneous)
- Energy Engineering and Power Technology
- Renewable Energy, Sustainability and the Environment
- Mechanical Engineering