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Full-Text Articles in Nuclear Engineering
Two-Equation Two-Fluid Model For Bubbly Flow In A Vertical Channel, Jeffrey Feliszak, Martin Bertodano
Two-Equation Two-Fluid Model For Bubbly Flow In A Vertical Channel, Jeffrey Feliszak, Martin Bertodano
The Summer Undergraduate Research Fellowship (SURF) Symposium
The one-dimensional two-fluid model is widely acknowledged as the most detailed and accurate macroscopic formulation of the thermo-fluid dynamics in nuclear reactor safety analysis. Several thermo-fluid dynamics codes have sprung up based on the one dimensional two-fluid model, such as RELAP5, TRAC, RETRAN, CATHARE, etc. However, these codes are quasi-steady because they lack the short wavelength models that are necessary to make the models well-posed; therefore they must rely on excessive numerical viscosity. Not utilizing short wavelength models causes small wavelength waves to grow quickly to infinity. The project objective is to develop a drafting force model for a one …