Exploració per tema "Àrees temàtiques de la UPC::Energies::Energia nuclear::Reactors nuclears de fissió"

Ara es mostren els items 1-13 de 13

    • 237-Np(n,f) cross section: new data and present status 

      Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme (2011-08-12)
      Article
      Accés restringit per política de l'editorial
      In this document, we present the nal result obtained at the n TOF experiment for the neutron- induced ssion cross section of the 237Np, from the ssion threshold up to 1 GeV. The method applied to get this result is ...

    • 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)
      Projecte Final de Màster Oficial
      Accés restringit per decisió de l'autor
      Realitzat a/amb:   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. ...

    • Design and Installation Challenges of the Neutral Beam Absorbers for the Large Hadron Collider at CERN 

      Fernández Vélez, Óscar (Universitat Politècnica de Catalunya, 2005-06)
      Projecte/Treball Final de Carrera
      Accés obert

    • Electromagnetic process to purify nuclear molten salts 

      Mestre Molist, Marta (Universitat Politècnica de Catalunya / Institut National Polytechnique de Grenoble, 2011)
      Projecte/Treball Final de Carrera
      Accés restringit per decisió de l'autor
      The separation between actinides and fission products could be realized by a pyrometallurgical liquid/liquid extraction process. Thanks to an oxide-reductive reaction, a mass exchange occurs at the interface between a ...

    • Estudio de los parámetros de transferencia de calor y de degradación del núcleo de un reactor PWR. Ajuste del modelo utilizado 

      Jourdan, Samuel (Universitat Politècnica de Catalunya, 2005-05)
      Projecte/Treball Final de Carrera
      Accés obert

    • 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
      Accés restringit per política de l'editorial
      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 ...

    • Highly accurate measurements of the spontaneous fission half-life of 240,242Pu 

      Salvador Castiñeira, Paula Genoveva; Brys, Tomasz; Eykens, Roger; Hambsch, Franz Josef; Moens, André; Oberstedt, Stephan; Sibbens, Geodele; Vanleeuw, David; Vidali, Marzio; Pretel Sánchez, Carme (2013-12-18)
      Article
      Accés restringit per política de l'editorial
      Fast spectrum neutron-induced fission cross-section data for transuranic isotopes are of special demand from the nuclear data community. In particular highly accurate data are needed for the new generation IV nuclear ...

    • Measurement of the Pu-240,242 neutron-induced fission cross sections 

      Salvador-Castiñeria, P; Bevilacqua, R; Brys, T; Hambsch, FJ; Oberstedt, S; Pretel Sánchez, Carme; Vidali, M (2012)
      Comunicació de congrés
      Accés restringit per política de l'editorial

    • Modelling and evaluating the consequences of the presence of O2− in NaF–ZrF4 molten fluoride salt 

      Andreu Pedrosa, Guillem (Universitat Politècnica de Catalunya / Sorbonne univesités. Université Pierre et Marie Curie, 2011)
      Projecte/Treball Final de Carrera
      Accés obert
      The framework of this study is the potential use of molten salts in the nuclear industry of the future. Those systems properties have been determined from finite temperature molecular dynamics simulations with a realistic ...

    • Neutron-induced fission cross section of 245-Cm: New results from data taken at the time-of-flight facility n_TOF 

      Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme (2012-03-29)
      Article
      Accés restringit per política de l'editorial
      The neutron-induced fission cross section of 245Cm was measured at n_TOF in a wide energy range and with high resolution. The energy dependence, measured in a single measurement from 30 meV to 1 MeV neutron energy, has ...

    • Neutron-induced fission cross section of Pu-240 from 0.5 MeV to 3 MeV 

      Salvador Castiñeira, Paula Genoveva; Brys, Tomasz; Eykens, Roger; Hambsch, Franz Josef; Gook, A.; Moens, André; Oberstedt, Stephan; Sibbens, Geodele; Vanleeuw, David; Vidali, Marzio; Pretel Sánchez, Carme (2015-07-21)
      Article
      Accés obert
      Pu-240 has recently been pointed out by a sensitivity study of the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency (NEA) to be one of the isotopes whose fission cross section lacks accuracy ...

    • Neutron-induced fission cross sections of Pu-242 from 0.3 MeV to 3 MeV 

      Salvador Castiñeira, Paula Genoveva; Brys, Tomasz; Eykens, Roger; Hambsch, Franz Josef; Gook, A.; Moens, André; Oberstedt, Stephan; Sibbens, Geodele; Vanleeuw, David; Vidali, Marzio; Pretel Sánchez, Carme (2015-10-13)
      Article
      Accés obert
      The majority of the next generation of nuclear power plants (GEN-IV) will work in the fast-neutron-energy region, as opposed to present day thermal reactors. This leads to new and more accurate nuclear-data needs for some ...

    • Neutron-induced fission cross-section of U-233 in the energy range 0.5 < E-n < 20 MeV 

      Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme (2011-01)
      Article
      Accés restringit per política de l'editorial
      The neutron-induced fission cross-section of 233U has been measured at the CERN n TOF facility relative to the standard fission cross-section of 235U between 0.5 and 20MeV. The experiment was performed with a fast ...