Now showing items 21-34 of 34

    • Implementation of dynamic nuclear fuel thermo-mechanics in transient simulation of lead-cooled reactors 

      Aragon Grabiel, Pau (Universitat Politècnica de Catalunya, 2021-11-01)
      Master thesis
      Open Access
      The nuclear industry must address the issues faced by the current new-built plants in the west- ern world if it is to remain cost-competitive with other forms of electricity generation. Serial, factory-based production of ...
    • Influence of the Fukushima Dai-ichi nuclear accident on Spanish environmental radioactivity levels 

      Baeza, A.; Corbacho, J.A.; Rodríguez, Alicia; Galván, J.; García Tenorio, R.; Manjón, G.; Mantero, Juan; Vioque, I.; Arnold Arias, Dèlia; Grossi, Claudia; Serrano Carreño, M. Isabel; Valles Murciano, M. Isabel; Vargas Drechsler, Arturo (Elsevier, 2012-12)
      Article
      Restricted access - publisher's policy
      This paper presents measurements of the effect of the atmospheric radioactive release from the Fukushima Dai-ichi nuclear power station at three sites belonging to the Spanish environmental monitoring system. Measured ...
    • Interfície gràfica per al simulador “Safaly” 

      Tous Nadal, Joan (Universitat Politècnica de Catalunya, 2006-06-14)
      Master thesis (pre-Bologna period)
      Open Access
      El codi SAFALY s'utilitza per als estudis de seguretat del reactor ITER. És important la participació en aquest projecte de professors i estudiants especialitzats en temes informàtics per millorar la interfície gràfica ...
    • Measurement of the 236U(n, f ) cross section from 170 meV to 2 MeV at the CERN n TOF facility 

      Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme (2011-10-31)
      Article
      Restricted access - publisher's policy
      The neutron-induced fission cross section of 236U was measured at the neutron Time-of-Flight (n TOF) facility at CERN relative to the standard 235U(n,f ) cross section for neutron energies ranging from above thermal ...
    • Measurement of the 241Am neutron capture cross section at the n TOF facility at CERN 

      Mendoza, E.; Cano-Ott, D; Altstadt, Sebastian; Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Gómez Hornillos, María Belén; Riego Pérez, Albert (EDP Sciences, 2016)
      Conference report
      Open Access
      New neutron cross section measurements of minor actinides have been performed recently in order to reduce the uncertainties in the evaluated data, which is important for the design of advanced nuclear reactors and, in ...
    • Measurement of the 90,91,92,93,94,96-Zr(n,gamma) and 139-La(n,gamma) cross sections at n TOF 

      Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme (EDP Sciences, 2007)
      Conference report
      Open Access
      Neutron capture cross sections of Zr and La isotopes have important implications in the field of nuclear astrophysics as well as in the nuclear technology. In particular the Zr isotopes play a key role for the determination ...
    • Measurement of the neutron-induced fission cross-section of 243Am relative to 235U from 0.5 to 20 MeV 

      Belloni, F.; Calviani, M.; Colonna, N.; Mastinu, P.; Milazzo, P.M.; Abbondanno, U.; Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme (2011-12)
      Article
      Restricted access - publisher's policy
      The ratio of the neutron-induced fission cross-sections of 243Am and 235U was measured in the energy range from 0.5 to 20 MeV with uncertainties of ≈4%. The experiment was performed at the CERN n TOF facility using a ...
    • Multimedia on nuclear reactor physics 

      Dies Llovera, Javier; Puig, Francesc (2010-06-21)
      Conference lecture
      Open Access
    • New measurement of the 242Pu(n,gamma) cross section at n TOF-EAR1 for MOX fuels: Preliminary results in the RRR 

      Lerendegui-Marco, J.; Guerrero, C.; Cortés-Giraldo, M.A.; Calviño Tavares, Francisco; Casanovas Hoste, Adrià; Cortés Rossell, Guillem Pere; Gómez Hornillos, María Belén; Tarifeño Saldivia, Ariel Esteban (EDP Sciences, 2016)
      Conference lecture
      Open Access
      The spent fuel of current nuclear reactors contains fissile plutonium isotopes that can be combined with 238U to make mixed oxide (MOX) fuel. In this way the Pu from spent fuel is used in a new reactor cycle, contributing ...
    • On the use of a dedicated ballast pellet for a prompt self-ejection mechanism after a temperature transient in lead-cooled fast reactors 

      Arias Montenegro, Francisco Javier (2017-10)
      Article
      Open Access
      The potential use of changes in buoyancy as a reactivity feedback mechanism during temperature transients in heavy liquid metal fast reactors (HLMFRs) is discussed. It is shown that with the use of ballast pellets (~15% ...
    • PLACA/DPLACA: código para la simulación del comportamiento de un combustible tipo placa monolítico/disperso 

      Soba, Alejandro; Denis, Alicia (Universitat Politècnica de Catalunya, 2007)
      Article
      Open Access
      Se presentan los códigos PLACA/DPLACA desarrollados para la descripción del comportamiento bajo irra-diación de elementos combustibles del tipo de los utilizados en reactores nucleares de investigación. PLACA en sus dos ...
    • Qualification of Spatial Coupling of System Reactor Simulators for BWR Stability 

      Alfonso Prieto-Puga, Elsa de (Universitat Politècnica de Catalunya / Kungliga Tecniska Högskolan, 2008)
      Master thesis (pre-Bologna period)
      Restricted access - confidentiality agreement
    • Safety regulations of fuzzy-logic control to nuclear reactors 

      Ruan, Da (Universitat Politècnica de Catalunya. Secció de Matemàtiques i Informàtica, 2000)
      Article
      Open Access
      We present an R&D project on fuzzy-logic control applications to the Belgian Nuclear Reactor 1 (BR1) at the Belgian Nuclear Research Centre (SCK•CEN). The project started in 1995 and aimed at investigating the added ...
    • Small Modular Reactor (SMR) innovation project 

      Moreno Martínez, Pedro (Universitat Politècnica de Catalunya, 2019-11-28)
      Master thesis
      Restricted access - author's decision
      Covenantee:   École centrale de Paris / Assystem
      In the context of a global crisis due to theconsequences of climate change,the Nuclear Energy shows itself as akey factor in the mitigation of the devastating effects that the emission of greenhouse gases are causing.The ...