Now showing items 1-5 of 5

    • Analysis of nuclear fusion reactor discharge simulations using METIS 

      Guilera Alonso, Xavier (Universitat Politècnica de Catalunya, 2023-02-13)
      Bachelor thesis
      Open Access
      The Nuclear Engineering Department of UPC has the need of a nuclear fusion plasma simulator for its research activities and educational tasks. For many years, PRETOR has been the program used for this purpose, but it has ...
    • Estudio de criticidad del reactor MSBR con SCALE 

      Criado Martín, Alejandro Fernando (Universitat Politècnica de Catalunya, 2011-05)
      Master thesis (pre-Bologna period)
      Open Access
      El presente proyecto final de carrera se enmarca en el convenio de colaboración entre el Consejo de Seguridad Nuclear (CSN) y la Universitat Politècnica de Catalunya (UPC) para la realización de proyectos en el ámbito ...
    • Monte Carlo time dependent modeling of the MYRRHA core based on SERPENT2 

      Ballester Vázquez, Bernat (Universitat Politècnica de Catalunya, 2022-05-18)
      Master thesis
      Open Access
      Els fenòmens transitoris són de gran importància per a l’anàlisi de seguretat en nous dissenys de reactors. Actualment, amb MYRRHA en procés de ser llicenciat, enginyers i científics a l’SCK CEN estan fent tots els estudis ...
    • Multiphysics simulations of Molten Salt Reactors using the Moltres code 

      Pater, Mateusz (Universitat Politècnica de Catalunya, 2019-11-28)
      Master thesis
      Open Access
      Covenantee:   Université Paris-Saclay
      The aim of this paper was to model and simulate Molten Salt Reactor (MSR) specific phenomena, to analyzethem on an example of two different MSR designs, and to assess the accuracy of different codes.Although inherent safety ...
    • Use of the simulation code METIS to analyze a balance of power in ITER. 

      Billette De Villemeur, Max (Universitat Politècnica de Catalunya, 2023-07-17)
      Tutored research work
      Open Access
      This research assignment is a power balance in the International Thermonuclear Experimental Reactor (ITER). First it describes summarily the different components of the reactor, the power input and output, and the tools ...