Recent Submissions

  • Analysis of flow channel insert deformations influence on the liquid metal flow in DCLL blanket channels 

    Di Giulio, Dionisio; Suárez Cambra, Daniel; Batet Miracle, Lluís; Mas de les Valls Ortiz, Elisabet; Savoldi, Laura (2020-08-01)
    Article
    Restricted access - publisher's policy
    The dual coolant lithium lead (DCLL) is a candidate to be an effective breeding blanket (BB) concept for nuclear fusion technologies. One critical point of this design is the magnetohydrodynamic (MHD) effects involving ...
  • Measurement of the a ratio and (n,¿) cross section of U 235 from 0.2 to 200 eV at n_TOF 

    Balibrea-Correa, J.; Mendoza, E.; Cano Ott, Daniel; Capote Noy, Roberto; Altstadt, Sebastian; Andrzejewski, Józef; Audouin, Ludmila; Bécares, Vicente; Barbagallo, Massimo; Becvar, F.; Belloni, Fabio; Berthoumieux, Eric; Billowes, J.; Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Gómez Hornillos, María Belén (American Physical Society, 2020-10-20)
    Article
    Open Access
    We measured the neutron capture-to-fission cross-section ratio (a ratio) and the capture cross section of 235U between 0.2 and 200 eV at the n_TOF facility at CERN. The simultaneous measurement of neutron-induced capture ...
  • A first prototype of C6D6 total-energy detector with SiPM readout for neutron capture time-of-flight experiments 

    Balibrea-Correa, J.; Lerendegui Marco, Jorge; Calvo Diaz-Aldagalán, David; Caballero Ontanaya, Luis; Babiano Suárez, Víctor; Tolosa Delgado, Alvaro; Domingo Pardo, César; Calviño Tavares, Francisco; Tarifeño Saldivia, Ariel Esteban; Casanovas Hoste, Adrià; Cano Ott, Daniel; Alcayne Aicua, Víctor; Bacak, Michael; Barbagallo, Massimo (2021-01-01)
    Article
    Open Access
    Low efficiency total-energy detectors (TEDs) are one of the main tools for neutron capture cross section measurements utilizing the time-of-flight (TOF) technique. State-of-the-art TEDs are based on a CD liquid-scintillation ...
  • Minimizing the standard deviation of the thermal load in the spent nuclear fuel cask loading problem 

    Bautista Valhondo, Joaquín; Batet Miracle, Lluís; Mateo Doll, Manuel (2020-09-17)
    Article
    Open Access
    The paper assumes that, at the end of the operational period of a Spanish nuclear power plant, an Independent Spent Fuel Storage Installation will be used for long-term storage. Spent fuel assemblies are selected and ...
  • Advanced tools for ITER Tritium Plant System Modeling & Design 

    Nougués, José María; Feliu, Josep Anton; Campanyà, Gerard; Iraola de Acevedo, Eduardo; Batet Miracle, Lluís; Sedano Miguel, Luis Ángel (2020-01-01)
    Article
    Open Access
    Chemical plant system modeling experience based on the use of largely validated commercial modeling tools such as the Aspen HYSYS is adapted and exploited to develop numeric routines for unitary isotopic operations, including ...
  • 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 ...
  • A compact fission detector for fission-tagging neutron capture experiments with radioactive fissile isotopes 

    Bacak, Michael; Aiche, Mourad; Bélier, Gilbert; Berthoumieux, Eric; Diakaki, Maria; Dupont, Emmeric; Gunsing, Frank; Kopecky, Stefan; Calviño Tavares, Francisco; Casanovas Hoste, Adrià; Cortés Rossell, Guillem Pere; Tarifeño Saldivia, Ariel Esteban (2020-04-21)
    Article
    Open Access
    In the measurement of neutron capture cross-sections of fissile isotopes, the fission channel is a source of background which can be removed efficiently using the so-called fission-tagging or fission-veto technique. For ...
  • Investigation of the 240Pu (n, f) reaction at the n_TOF/EAR2 facility in the 9 meV–6 MeV range 

    Stamatopoulos, A.; Tsinganis, Andrea; Colonna, Nicola; Vlastou, Roza; Diakaki, Maria; Žugec, Petar; Gunsing, Frank; Sabaté-Gilarte, Marta; Barbagallo, Massimo; Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere (American Physical Society (APS), 2020-07-21)
    Article
    Open Access
    Background: Nuclear waste management is considered amongst the major challenges in the field of nuclear energy. A possible means of addressing this issue is waste transmutation in advanced nuclear systems, whose operation ...
  • Modelado y resolución del problema del encapsulamiento de combustible nuclear gastado 

    Bautista Valhondo, Joaquín; Batet Miracle, Lluís; Mateo Doll, Manuel (2020-07-16)
    Article
    Open Access
    En la gestión de residuos de combustible de las centrales nucleares españolas, está previsto activar los almacenes temporales individualizados (ATI) cuando se alcanza la saturación de la piscina destinada a albergar elementos ...
  • Modelling guidelines for safety analysis of Station Black Out sequences based on experiments at the PKL test facility 

    Freixa Terradas, Jordi; Martínez Quiroga, Víctor Manuel; Reventós Puigjaner, Francesc Josep (2020-04-01)
    Article
    Restricted access - publisher's policy
    After the Fukushima accident, “stress-test” activities carried out worldwide pointed out the need to study additional accident management measures to deal with prolonged Station Black Out (SBO) scenarios. Without any ...
  • Measurement of the 154Gd(n,gamma) cross section and its astrophysical implications 

    Mazzoni, Alberto; Cristallo, Sergio; Aberle, O.; Alcayne Aicua, Víctor; Amaducci, Simone; Andrzejewski, Józef; Audouin, Ludmila; Calviño Tavares, Francisco; Casanovas Hoste, Adrià; Cortés Rossell, Guillem Pere; Tarifeño Saldivia, Ariel Esteban (Elsevier, 2020-05-10)
    Article
    Open Access
    The neutron capture cross section of 154Gd was measured from 1 eV to 300 keV in the experimental area located 185 m from the CERN n_TOF neutron spallation source, using a metallic sample of gadolinium, enriched to 67% in ...
  • Simultaneous measurement of neutron-induced capture and fission reactions at CERN 

    Guerrero, C.; Berthoumieux, Eric; Cano-Ott, D; Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Gómez Hornillos, María Belén (2012)
    Article
    Open Access
    The measurement of the capture cross-section of fissile elements, of utmost importance for the design of innovative nuclear reactors and the management of nuclear waste, faces particular difficulties related to the -ray ...

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