• 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)
    Text en actes de congrés
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    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 ...
  • 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 Angel (2014-04-01)
    Article
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    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)
    Comunicació de congrés
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    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)
    Comunicació de congrés
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    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)
    Text en actes de congrés
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    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 ...