Sökning: "CFD nuclear"
Visar resultat 1 - 5 av 21 uppsatser innehållade orden CFD nuclear.
1. Computational Fluid Dynamics and Modeling of a Free Surface Flow
Master-uppsats, KTH/Skolan för teknikvetenskap (SCI)Sammanfattning : This project deals with the CFD modelling of a free surface flow. The aim is to develop and validate a fast and accurate numerical model for stratified two-phase flows. Volume of Fluid (VOF) multiphase model is employed. The purpose is to use the developed numerical model for the design of an element within a compact nuclear reactor. LÄS MER
2. Investigation of coarse-grid CFD approach for nuclear engineering application
Master-uppsats, KTH/FysikSammanfattning : In this thesis, an innovative coarse grid CFD approach is developed that aims toexploit the capabilities of sub-channel codes and CFD methods while overcoming theirlimitations. In the approach, a very coarse mesh is implemented in the CFD softwareOpenFOAM and a new wall treatment, based on the traditional concept of the wallfunction, is applied to the wall boundary conditions of the domain to take into accountthe low resolution of the grid which does not allow to effectively capture the effect of thesolid walls on the thermo-hydraulics of the flow. LÄS MER
3. CFD Analysis of the Flow Into a Preheater
Master-uppsats, KTH/Teknisk mekanikSammanfattning : This project has investigated and formed a basis for the thermal- and flow-induceddynamic loads in the lower parts of a preheater situated in a nuclear power plant.Special attention has been given to the bottom plate that separates the heated andnon-heated secondary steam. LÄS MER
4. Thermal Hydraulics Simulations for Nuclear Energy
Master-uppsats, Uppsala universitet/Tillämpad kärnfysikSammanfattning : .... LÄS MER
5. Two-phase CFD Modelling and Validation : SH204X Master Thesis Project Report
Master-uppsats, KTH/KärnenergiteknikSammanfattning : This project deals with two-phase CFD model validation, a subject which is currently under active research due to its complexity. The goal is to create a model that predicts data profiles to an acceptable degree for a wide array of flow conditions. The applications within the nuclear field would mainly be for safety analysis, e.g. LÄS MER