Diplom

  • Acher, Thomas
    Numerische Simulation der Hydrodynamik von Blasensäulen mit dem Programmpaket OpenFOAM 
  • Alberdi, Gonzalo Valles
    Analysis of the Pressure Drop Model in Trace under Application of the BFBT NUPEC Data
  • Augier, Victor
    Hydraulic studies of the borication system (REA) of the French EPR of Flamanville
  • Bachschuster, Stefan
    Development of an OpenFOAM Solver able to Simulate Direct Contact Condensation
  • Barbed, Martin Ingo
    CFD study of Direct Contact Condensation in 3-D two-phase flows and its application to the security analysis of a LOCA in a PWR Nuclear Power Plant
  • Ben Ayed, Mourad
    Generische Fragestellung im Bereich sicherheitsrelevante Kopplung zwischen Kernkraftwerken und elektrischen Netz
  • Cardella, Umberto
    Loss of Intermediate Cooling in an innovative Sodium Fast Reactor - The Effect of Fuel Type Cepeda
  • Salido, Florentino Estudio
    Crítico del Ciclo del Torio Basado en un Combustible de Torio Cermet y Viabilidad Económica.
  • Ceuca, Sabin Cristian
    Untersuchungen von Identifikationsmethoden zur Anpassung des Teilsimulations "Reaktorkern"
  • Chemnitz, Tobias
    Commissioning and Characterization of an Improved Setup for the NECTAR Experiment.
  • Dackermann, Uwe
    ANSYS CFX 11 SP1 Mesh Sensitivity Analysis and Single Phase Pressure Drop Modeling of the OECD/NEA BFBT Benchmark
  • Dawedeit, Christoph
    Thick Nano-Crystalline Diamond films for fusion applications
  • Däubler, Miriam
    New Approach to Safety Analysis of FRM II
  • Fabre, Yannick
    Development of subgrid models for large-eddy simulations of a passive scalar in turbulent flows
  • Fernandez, Jesus Juanas
    Analysis de Incertidumbre y Sensibilidad en la Generacion de Parametros Neutronicos para Simulaciones Acopladas Termo-Hidraulica y Neutronicamente de Centrales Nucleares
  • Geffray, Clotaire
    Set-up of a suitable Input Deck for the Simulation of Small Break Loss of Coolant Accident in a generic Pressurized Water Reactor
  • González Martí, Marta
    Assessment and further development of programs for medical therapy using fission neutrons
  • Guillermo Orozco, Gijon
    Study of the hydraulic Properties of the Components in the Plasma Vessel of the Wendelstein 7-X and of its Cooling System.
  • Herrera-Garcia, Jorge Alberto
    CFD-Calculation of 2-Phase-Flow Phenomena inside the pump bending loop during LOCA in PWRs
  • Kath, David
    Untersuchungen zur adaptiven Simulation von Leistungstransienten in DWR unter Nutzung unmittelbar und verzögert erfasster Informationen
  • López-Gutiérrez, Francisco
    Development of High Heat Flux Mirrors for the High Power Electron Cyclotron Resonant Heating of Thermonuclear Fusion Devices
  • Marendet, Anais
    Modeling of heat transfer for a supercritical fluid in a one-dimensional pipe during a presure transient.
  • Mateo, Moreno
    Pròsper Experimental investigation of air bubble train in still distilled water under atmospheric pressure and room temperature
  • Moner, Guim Pallàs
    Study of a PWR Fuel Assembly Model in 2D & 3D during Core Irradiation using the Inventory Calculation System KENOREST
  • Morf, Christoph Emmanuel
    Sensitivitäts- und Unsicherheitsanalyse eines gekoppelten TRACE/PARCS Modells für die Siedewasserreaktor-stabilitätsanalyse
  • Navas, Sara Cuerva
    Modeling of a PWR Core, Few Group Parameters Generation and Criticality Calculation
  • Plank, Clemens
    Hydrogen Deflagration with Detailed Chemistry
  • Pradel, Sebastian
    Aufbau und Konstruktion Heißstrang-DWR für Untersuchungen des Gegenstrom-Begrenzungsphänomenes
  • Reitzer, Reinhold
    Entwicklung eines Transformationsverfahrens instationärer Temperaturfelder für Kraftwerkskomponenten
  • Röttgen, Carsten
    Enhancement and Evaluation of the Monte Carlo Depletion Code MONTEBURNS
  • Salanitro, Emmanuele Pietro
    CFD-Modellierung eines vereinfachten Siedewasserreaktorunterkanals mit Brennstab und Abstandshalter
  • Schenk, Robert
    Entwicklung und Konstruktion eines Lamellenkollimators für die Neutronentherapie
  • Schiefer, Stefanie
    Validierung des Programms CASMO-4 mittels Folienaktivierung hinsichtlich der Reaktionsratenverteilungen in Uranoxid-Brennstäben für eine Brennstabanordnung der Generator IV (High Performance Light Water Reactor)
  • Schmid, Wolfgang
    Efficient application of variance reduction methods in Monte Carlo simulation of the photoneutron contamination in medical LINAC beams
  • Sureda, Antonio Jaime Sureda
    Generic Investigations on Transport Theory Modelling of High Temperature Reactors of Pepple Bed Type
  • Türk, Robert
    Physical Properties of highly burnt Uranium Oxid and MOX PWR Fuels: Validation of Composition and Neutron Sources
  • Wanninger, Andreas
    CFD Simulations of Direct Contact Condensation with Surface Renewal Theory based Heat Transfer Coecients using ANSYS CFX
  • Weis, Johannes
    Computational Fluid Dynamics Analysis of a ROSA cold Leg Stratification Test
  • Weisensee, Patricia
    Experimental Investigation of Steam Bubble Condensation in Subcooled Flowing Water