CFD modelling of two-phase critical flow with different length to diameter ratio horizontal tubes
Singh, Sharandeet (2024)
Diplomityö
2024
School of Energy Systems, Energiatekniikka
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Julkaisun pysyvä osoite on
https://urn.fi/URN:NBN:fi-fe2024061753534
https://urn.fi/URN:NBN:fi-fe2024061753534
Tiivistelmä
In this master's thesis, two-phase critical flow in a separate effect test facility is investigated using computational fluid dynamics (CFD). This topic is being conducted as part of the CFLOW SAFER 2028 (National Nuclear Safety and Waste Management Research Program 2023–2028) project, which attempts to improve nuclear reactor safety and security.
It is reasonably necessary to understand the behavior of two-phase critical flow for the design and analysis of nuclear power systems, especially in emergency situations such as loss-of-coolant accidents. The prediction and understanding of fluid dynamics in nuclear power plants is quite essential for the safe and secure operation of the plants.
The main purpose of the thesis is to develop a comprehensive CFD model capable of simulating the flashing flow in pipes with different length-to-diameter ratios and to know the inception of flashing. To do this, ANSYS-FLUENT software, a commercial CFD simulation program, has been employed. Moreover, we performed in-depth analyses and examine the effects of various geometrical parameters, operational conditions, and turbulence models on the flow behavior.
Results from the simulations give us an insight into the inception of the flashing conditions along with the temperature, pressure and mass flow changes happening through the length of the pipe of different length-to-diameter ratios. Further, a comparison between the CFD and APROS results has been made to analyze the difference and similarities between these two different codes.
It is reasonably necessary to understand the behavior of two-phase critical flow for the design and analysis of nuclear power systems, especially in emergency situations such as loss-of-coolant accidents. The prediction and understanding of fluid dynamics in nuclear power plants is quite essential for the safe and secure operation of the plants.
The main purpose of the thesis is to develop a comprehensive CFD model capable of simulating the flashing flow in pipes with different length-to-diameter ratios and to know the inception of flashing. To do this, ANSYS-FLUENT software, a commercial CFD simulation program, has been employed. Moreover, we performed in-depth analyses and examine the effects of various geometrical parameters, operational conditions, and turbulence models on the flow behavior.
Results from the simulations give us an insight into the inception of the flashing conditions along with the temperature, pressure and mass flow changes happening through the length of the pipe of different length-to-diameter ratios. Further, a comparison between the CFD and APROS results has been made to analyze the difference and similarities between these two different codes.