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