Sökning: "Walter Villanueva"
Visar resultat 1 - 5 av 6 avhandlingar innehållade orden Walter Villanueva.
1. Diffuse-Interface Simulations of Capillary Phenomena
Sammanfattning : Fluid flows mainly driven by capillary forces are presented in this thesis. By means of modeling and simulations, interesting dynamics in capillary-driven flows are revealed such as coalescences, breakups, precursor films, flow instabilities, rapid spreading, rigid body motions, and reactive wetting. LÄS MER
2. CFD Study of Molten Pool Convection in a Reactor Vessel during a Severe Accident
Sammanfattning : During severe accidents in nuclear reactors, the core and internal structures can melt down and relocate into the reactor pressure vessel (RPV) lower head (LH) forming there a stratified molten corium pool. The pool generally consists of superheated oxidic and metallic liquid layers imposing thermo-mechanical loads on the RPV wall. LÄS MER
3. Steam condensation in a water pool and its effect on thermal stratification and mixing
Sammanfattning : The Pressure Suppression Pool (PSP) of a Boiling Water Reactor (BWR) is a large heat sink designed to limit the containment pressure by condensing steam released from the primary coolant system. The development of thermal stratification is a safety concern since it leads to higher containment pressures than in completely mixed conditions, and can affect the performance of systems such as the emergency core cooling and containment spray, which the use PSP as a source of water. LÄS MER
4. Validation and Application of CFD to Safety-Related Phenomena in Lead-Cooled Fast Reactors
Sammanfattning : Carbon-free nuclear power production can help to relieve the increasing energy demand in the world. New generation reactors with improved safety, sustainability, reliability, economy and security are being developed. Lead-cooled fast reactor (LFR) is one of them. LÄS MER
5. Thermo-mechanical Assessment of Reactor Pressure Vessels of Light Water Reactors During Severe Accidents
Sammanfattning : The reactor pressure vessel (RPV) is one of the crucial safety barriers designed to isolate the reactor core, safeguarding against potential radioactive releases into the environment during a severe accident. The assessment of RPV behaviour and its failure is necessary to predict the characteristics of melt release into the reactor pit and succeeding ex-vessel accident progression. LÄS MER