Now showing items 1-20 of 34

    • A negative reactivity feedback driven by induced buoyancy after a temperature transient in lead-cooled fast reactors 

      Arias Montenegro, Francisco Javier (2017-10-24)
      Article
      Open Access
      Consideration is given to the possibility to use changes in buoyancy as a negative reactivity feedback mechanism during temperature transients in heavy liquid metal fast reactors (HLMFRs). It is shown that by the proper ...
    • A new ion cyclotron range of frequency scenario for bulk ion heating in deuterium-tritium plasmas: How to utilize intrinsic impurities in our favour 

      Kazakov, Ye O.; Ongena, Jozef; Van Eester, Dirk; Bilato, Roberto; Dumont, Rémi J.; Lerche, Ernesto A.; Mantsinen, Mervi; Messiaen, André M. (American Institute of Physics Publising LLC, 2015-08-24)
      Article
      Open Access
      A fusion reactor requires plasma pre-heating before the rate of deuterium-tritium fusion reactions becomes significant. In ITER, radiofrequency (RF) heating of He ions, additionally puffed into the plasma, is one of the ...
    • Applying UPC scaling-up methodology to the LSTF-PKL counterpart test 

      Martínez Quiroga, Víctor Manuel; Reventós Puigjaner, Francesc Josep; Freixa Terradas, Jordi (2014-03-02)
      Article
      Open Access
      In the framework of the nodalization qualification process and quality guarantee procedures and following the guidelines of Kv-scaled analysis and UMAE methodology, further development has been performed by UPC team resulting ...
    • ARGOS un reactor a la diagonal 

      Barca Salom, Francesc Xavier (2011-04-14)
      External research report
      Open Access
      El reactor Argos va funcionar des del 16 de gener de 1963 en què va aconseguir l’autorització provisional. Al 1976 el reactor fou aturat per exigències de la nova llei nuclear. Al 1987 es va procedir a la clausura i el ...
    • Assessment of the adequacy of RELAP5 system code for the simulation of IBLOCA transient scenarios for Pressurized Water Nuclear Reactors 

      Martín Gil, Kevin (Universitat Politècnica de Catalunya, 2019-06-21)
      Master thesis
      Restricted access - author's decision
      The assessment of the tools used for deterministic safety analysis and the compliance with the acceptance criteria in thermal-hydraulic analysis of Nuclear Power Plants (NPP) is based on three steps; the first is based on ...
    • Be-7(n,alpha)He-4 reaction and the cosmological lithium problem: measurement of the cross section in a wide energy range at n_TOF at CERN 

      Barbagallo, Massimo; Musumarra, A.; Cosentino, L.; Calviño Tavares, Francisco; Casanovas Hoste, Adrià; Cortés Rossell, Guillem Pere; Tarifeño Saldivia, Ariel Esteban (2016-10-03)
      Article
      Open Access
      The energy-dependent cross section of the Be7(n,alpha)He4 reaction, of interest for the so-called cosmological lithium problem in big bang nucleosynthesis, has been measured for the first time from 10 meV to 10 keV neutron ...
    • C-14 Production in Lead-Cooled Reactors 

      Muñoz Trallero, Andrea (Universitat Politècnica de Catalunya / Aalto University School of Science and Technology, 2010)
      Master thesis (pre-Bologna period)
      Open Access
      The increase in the energy consumption and the expected growth in the nuclear capacity make it necessary to look on for new technologies based in more sustainable and safe principles, such as lead-cooled reactors. This ...
    • CFD Analysis of Natural Circulation Behaviour in Molten Salts and Simulation of the Seaborg Test Loop 

      Ruscoe, Timothy Andrew (Universitat Politècnica de Catalunya, 2020-01-10)
      Master thesis
      Restricted access - author's decision
      Covenantee:   École nationale supérieure de techniques avancées / Seaborg Technologies
      As part of the research and development activities for Seaborg Technologies’ Compact Molten Salt Reactor (CMSR), experiments into natural circulation behaviour of molten nitrate salts are being conducted with a test loop. ...
    • Construction, Testing and Modelling of a litre-scale Sorption Heat Storage Reactor 

      De Carli, Paolo (Universitat Politècnica de Catalunya, 2020-12-24)
      Master thesis
      Restricted access - author's decision
      Covenantee:   Technische Universiteit Eindhoven
      In this work, a litre-scale sorption reactor setup has been built and tested. The components and sensors of the setup have been specified to allow the reproducibility of the setup and the tests information (such as initial ...
    • Contribución al Desarrollo de la Multimedia de Física de Reactores Nucleares 

      Garre Werner, Guillermo (Universitat Politècnica de Catalunya, 2016-09-08)
      Bachelor thesis
      Open Access
      El proyecto “Contribución al Desarrollo de la Multimedia de Física de Reactores Nucleares” es el resultado del trabajo ininterrumpido de muchos profesionales. Se enmarca en el programa de docencia de la Cyber Learning ...
    • Desarrollo del código de seguridad para reactores de fusión AINA 4 para los análisis de seguridad de los diseños europeos de DEMO 

      Baeza Pérez, Eduard; Blas del Hoyo, Alfredo de; Riego Pérez, Albert; Fabbri, Marco (2017)
      Conference lecture
      Restricted access - publisher's policy
      Durante los últimos diez años, el código de seguridad AINA ha sido desarrollado con el objetivo de evaluar la evolución del plasma y los esfuerzos padecidos por los componentes internos de la vasija en distintos reactores ...
    • 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 ...
    • Development of the safety code AINA for the European DEMO designs 

      Baeza Pérez, Eduard; Blas del Hoyo, Alfredo de; Riego Pérez, Albert; Fabbri, Marco (2018-04-30)
      Article
      Open Access
      In order to evaluate plasma evolution and in-vessel components strains, a safety code called AINA has been developing during the last ten years for different fusion reactors designs. This work describes the new AINA code ...
    • DNB and Void Fraction TRACE Model Validation with PSBT Experiments 

      Jara Heredia, Daniel (Universitat Politècnica de Catalunya / Kungliga Tecniska Högskolan, 2010)
      Master thesis (pre-Bologna period)
      Open Access
      The aim of the thesis is the assessment and validation of numerical models for the prediction of detailed subchannel distribution and departure from nucleate boiling (DNB) to a full scale data on a prototypical PWR rod ...
    • Estudi paramètric de la transferència de triti en canals de metall líquid sota camps magnètics per reactors de fusió nuclear. 

      Lampon Diestre, Cristina (Universitat Politècnica de Catalunya, 2019-06-05)
      Master thesis
      Restricted access - author's decision
      In the frame of nuclear fusion as a carbon-free source of energy, the project DEMO studies -among others- the feasibility of the Dual Coolant Lithium Lead (DCLL) breeding blanket. As one of the key features of the breeding ...
    • Expérience de purification par voie électromagnétique de sels fondus 

      Sorroche Cerezales, Carlos (Universitat Politècnica de Catalunya / Institut National Polytechnique de Grenoble, 2010)
      Master thesis (pre-Bologna period)
      Open Access
      Dans ce rapport, on analyse la possibilité d’utiliser l’agitation électromagnétique pour accélérer la purification des sels fondus d’un réacteur nucléaire de Génération IV. Pour cela, on utilise une technique d’extraction ...
    • Fission yield measurements from uranium irradiated in the VR-1 reactor 

      Sala León, Júlia (Universitat Politècnica de Catalunya, 2019-09-11)
      Master thesis
      Open Access
      Covenantee:   České vysoké učení technické v Praze
      This master thesis gives the theoretical description and practical measurement of fission yields from a sample of depleted uranium irradiated for 15 minutes in a research reactor, i.e. VR-1 reactor of the CTU in Prague. ...
    • High precision measurement of the radiative capture cross section of 238U at the n TOF CERN facility 

      Mingrone, Federica; Altstadt, Sebastian; Andrzejewski, Józef; Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Gómez Hornillos, María Belén; Riego Pérez, Albert (EDP Sciences, 2016)
      Conference report
      Open Access
      The importance of improving the accuracy on the capture cross-section of 238U has been addressed by the Nuclear Energy Agency, since its uncertainty significantly affects the uncertainties of key design parameters for both ...
    • High-energy neutron-induced fission cross sections of natural lead and bismuth-209 

      Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme (2011-08-12)
      Article
      Restricted access - publisher's policy
      The CERN Neutron Time-Of-Flight (n TOF) facility is well suited to measure small neutron- induced ssion cross sections, as those of subactinides. The cross section ratios of natPb and 209Bi relative to 235U and 238U ...
    • Hydrodynamics study inside microchannels (microreactors) 

      Clemente Bautista, Alex (Universitat Politècnica de Catalunya / Univerza Ljubljani, 2008)
      Master thesis (pre-Bologna period)
      Restricted access - confidentiality agreement