Master

  • Alali, Abdullah
    Implementing Advanced Boiling Models in the Development of FLUBOX - 3D Code
  • Albrecht, Florian
    Entwicklung einer Analysemethode für die Ermittlung des lokalen Leistungsverhalten in Siedewasserreaktortransienten
  • Alós Díez, Ana
    Structural Analysis of the Irradiation-Induced Behavior of the Fuel-Rod Support of a PWR Fuel Assembly using the Finite Element Method
  • Arredondo, Rodrigo
    Operation, Commissioning and Installation of a High-Speed Lithium Pellet Injector in the ASDEX Upgrade Fusion Reactor
  • Bai, Zijia
    Generation of a simplified PWR Fuel Assembly Model for CFD Calculations
  • Bassas, Jordi
    Development and implementation of a Nuclear Power Plant steam turbine model in the system code ATHLET
  • Cabrera Millán, Isabel
    Structural Analysis of the Irradiation-Induced Longitudinal Growth of a PWR Fuel Assembly during Normal Operation using the Finite Element Method
  • Capirone, Valerio
    Analysis of Thorium-Plutonium fuelled Nuclear Reactors
  • Carrasco Boix, Adriá
    3D CFD Simulations using the Lattice Boltzmann Method
  • Chenkai, Xu
    Simulation of multi phase flows, including the droplet-film interaction
  • Dackermann, Uwe
    Influence of Hydrogen on the Burst Behavior during Large Break Loss of Coolant Accidents of Zirconium Alloy Fuel Rod Claddings
  • Dibon, Mathias Martin
    Entwicklung und Verbesserung eines Blower Gun Pellet Injektors für die Anwendung in thermonuklearen Fusionsanlagen
  • Du, Zhuoqi
    The Risk-rewards Structure of Using Spent Fuel in Molten Salt Reactor
  • Ennab, Neil Abu
    Validation of the CASMO-PARCS calculation scheme for an experimental core
  • Fan, Rong
    CFD Strömungssimulationen mit freier Oberfläche und Kondensation
  • Freiria Lopez, Maria
    Options for the conversion of thr FRM II outside the core
  • Garrido-Lestache, Adoración
    Simulation of a NPP steam turbine with the best-estimate system code TRACE
  • Gómez, Vega
    Simulation of a NPP steam turbine with ATHLET system code
  • He, Xun
    TRACE Validation for the Natural Circulation of the Decay Heat Removal System of the Small Modular PWR: Nuscale
  • Kaiser, Nadine
    Validierung und klinische Inbetriebnahme des Softwaresystems COMPASS zur Verifikation von Patientenplänen in der Strahlentherapie
  • Kreß, Malte
    Characterization of the Stoichiometric Influence on the Material Properties of Chromium-Nitrogen Coatings
  • Larcher, Deimos
    New Tungsten Wire Calorimeters for the Negative Ion Source Testbeds ELISE and BATMAN-Upgrade: Design, Manufacturing and Data Analysis
  • Le Guennic, Clémentine
    Validation of a thermalhydraulic transient simulation code for the Evolutionary Power Reactor (EPR)
  • Li, Tianqi
    Further Development of a Generic Boiling Water Reactor Model for the Coupled Simulation with the Codes ATHLET / PARCS
  • Lopez Perez, Raul
    Study of Direct Contact Condensation in two-phase flows and its application to the security analysis of a LOCA in a PWR Nuclear Power Plants
  • Perez-Aradros, Jesus Rivero
    Test and Validation of the coupling between ATHLET and OpenFOAM using the example of Liquid Metal Cooling Systems
  • Pletz, Kevin
    Assessment of the Influence of Fuel Assembly Bow on the Behaviour of a PWR Core
  • Sevilla Padron, Angel
    Study and review of the current understanding of models for the simulation of vertical turbulent bubbly flow with CFD
  • Wang, Xiang
    Simulation für Betrieb und Störfall eines kleinen modularen Reaktors (SMR) mPower (DWR) mit ATHLET
  • Zhang, Yichao
    Uncertainty Analysis applied to the TALL Facility
  • Aparicio-Martinez, Javier
    EnriqueCFD Pre-test and Post-test Analysis of NGNP Reactor Cavity Cooling System
  • Demazeau, Franck
    Study of the suitability of ATHLET for the simulation of a Molten Salt Reactor
  • Martinez-Contreras, Luis Angel
    Static Analysis of Fuel Assembly Bow due to Neutron-Flux and Temperature Gradients in a PWR using the Finite Element Method
  • Dobmeier, Fabian Constantin
    Description and Fabrication of Uranium-Tungsten Alloys (U-W Alloys) in the Context of Accident Tolerant Fuels
  • Caballero, Luis Rafecas
    Optimization Study of a 2D CFD Porous Model for the Fluid-Structure Coupling of PWR Fuel Assemblies in the Reactor Core
  • Ruiz, Jaime
    Set up of a Fluid Structure Coupling Interface (FSI) between PWR fuel assemblies and the reactor coolant, based on a porous medium approach
  • Chiriac, Flavius
    Extension of the ATHLET- OpenFOAM Coupling Capabilities to Two-Phase Flows
  • Zuro, Oliva
    Analisis comparativo desistemas de seguridad de reactores PWR de 3a Generation
  • Gomez de la Rosa
    Simulation of NPP Steam turbine with ATHLET system code
  • Jorda-Sempere
    Estudio Tecnico Economico de Fabrication de un Tornillo de interferencia Basado en Acido polilactico (PLA) para reparacion
  • Jordan, Luis Palop
    Auslegung, Bewertungund Einsatzempfehlung eines berührgeschützten Kontaktierungssystems für Hochvolt-Traktionsbatterien