Now showing items 1-7 of 7

    • Application of a BEPU-based code assessment to the ATLAS upper head SB-LOCA test 

      Al Awad, Abdulrahman; Freixa Terradas, Jordi; Pérez-Ferragut, Marina (2021-12-15)
      Article
      Open Access
      The prevailing state of knowledge of two-phase flow in complex systems, as in the nuclear field, usually leads a certain degree of ad hoc calibration of computational models and the consequent inevitable subjectivity in ...
    • Aproximación multiescala a la simulación termohidráulica de reactores de fusión en la Universidad Politécnica de Cataluña 

      Batet Miracle, Lluís; Mas de les Valls Ortiz, Elisabet; Osychenko, Oleg; Martínez Quiroga, Víctor Manuel; Pérez-Ferragut, Marina; Freixa Terradas, Jordi; Reventós Puigjaner, Francesc Josep (2014)
      Conference report
      Restricted access - publisher's policy
      El Grupo de Estudios Termohidráulicos (GET) de la UPC posee gran experiencia en estudios de seguridad nuclear mediante códigos de simulación de plantas nucleares. Desde 1987, el grupo ha colaborado con las CN de Ascó y ...
    • Development of flow regime maps for lead lithium eutectic–helium flows 

      Mas de les Valls Ortiz, Elisabet; Cegielski, Andrzej; Jaros, Mark; Pérez-Ferragut, Marina; Batet Miracle, Lluís; Freixa Terradas, Jordi (2020-09-01)
      Article
      Restricted access - publisher's policy
      nstitute for Plasma Research (IPR), Gandhinagar (India) is currently involved in the design and development of its Lead-Lithium Ceramic Breeder (LLCB) module for testing in the International Thermo-nuclear Experimental ...
    • Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5-3D 

      Batet Miracle, Lluís; Álvarez Fernández, Josep Maria; Mas de les Valls Ortiz, Elisabet; Martínez Quiroga, Víctor Manuel; Pérez-Ferragut, Marina; Reventós Puigjaner, Francesc Josep; Sedano Miguel, Luis Ángel (2014-04-01)
      Article
      Restricted access - publisher's policy
      A supercritical recompression CO2 power cycle has been simulated using the system code RELAP5-3D. This code is being developed by INL and has traditionally been used in the simulation of operational and accidental transients ...
    • RELAP/SCDAPSIM/MOD4.0 modification for transient accident scenario of test blanket modules involving helium flows into heavy liquid metal 

      Pérez-Ferragut, Marina; Freixa Terradas, Jordi; Mas de les Valls Ortiz, Elisabet (2015)
      Conference lecture
      Restricted access - publisher's policy
      The Institute for Plasma Research (IPR), India, is currently involved in the design and development of its Test Blanket Module (TBM) for testing in ITER (International Thermo nuclear Experimental Reactor). The Indian TBM ...
    • Revisiting ISP-13 with RELAP/SCDAPSIM/MOD3.5 using core SCDAP components 

      Freixa Terradas, Jordi; Pérez-Ferragut, Marina; Reventós Puigjaner, Francesc; Allison, Chris M. (2015)
      Conference lecture
      Restricted access - publisher's policy
      The recent accident in the Fukushima Daiichi nuclear power plant opened a discussion on severe accident management that includes the analysis of the accident by means of computational tools that can predict the core behavior ...
    • Significance of the input parameters selection and the nodalization qualification in the final results of an IBLOCA BEPU calculation 

      Martínez Quiroga, Víctor Manuel; Freixa Terradas, Jordi; Pérez-Ferragut, Marina; Reventós Puigjaner, Francesc (2016)
      Conference report
      Restricted access - publisher's policy
      In the framework of Design Basis Accidents (DBA) for Pressurized Water Reactor (PWR), and based on recent studies on pipe integrity combined with the Risk-Informed Decision Making (RIDM), the USNRC proposed the Intermediate ...