Exploració per tema "Fusion reactors"

Ara es mostren els items 21-40 de 47

    • Dynamic study of a supercritical carbon dioxide power cycle for DEMO 

      Batet Miracle, Lluís; Linares, José Ignacio; Aulet Prieto, David; Cantizano González, Alexis; Griñó Cubero, Robert; Moratilla, Beatriz Y. (2016)
      Text en actes de congrés
      Accés restringit per política de l'editorial
      In the framework of the research program undertaken by the EUROFusion consortium (within H2020), the feasibility has been analysed of using a supercritical carbon dioxide Brayton cycle as the power conversion system in a ...

    • Effect on the Tritium Breeding Ratio for a distributed ICRF antenna in a DEMO reactor 

      Garcia Perez, Albert (Universitat Politècnica de Catalunya, 2015-09)
      Projecte/Treball Final de Carrera
      Accés restringit per decisió de l'autor
      This thesis reports results of MCNP-5 calculations, with the nuclear data library FENDL-2.1, to assess the effect on the Tritium Breeding Ratio (TBR) when integrating a distributed Ion Cyclotron Range of Frequencies (ICRF) ...

    • Estudi paramètric de la transferència de triti en canals de metall líquid sota camps magnètics per reactors de fusió nuclear. 

      Iraola de Acevedo, Eduardo; Lampon Diestre, Cristina (Universitat Politècnica de Catalunya, 2019-01-17)
      Projecte Final de Màster Oficial
      Accés restringit per decisió de l'autor

    • Experimental confirmation of efficient island divertor operation and successful neoclassical transport optimization in Wendelstein 7-X 

      Sunn Pedersen, Thomas; Abramovic, Ivana; Agostinetti, Piero; Agredano Torres, Manuel; Äkäslompolo, Simppa; Alcuson Belloso, Jorge; Aleynikov, Pavel; Caminal Colell, Ivan; Casas Pla, Josep Ramon; Salembier Clairon, Philippe Jean (2022-04-01)
      Article
      Accés obert
      We present recent highlights from the most recent operation phases of Wendelstein 7-X, the most advanced stellarator in the world. Stable detachment with good particle exhaust, low impurity content, and energy confinement ...

    • Extrapolations of the fusion performance in JET 

      Gallart, Daniel; Mantsinen, M.J.; Garzotti, L.; Challis, C.; Garcia, J.; Gutiérrez, A.; Sáez, X. (Barcelona Supercomputing Center, 2015-05-05)
      Text en actes de congrés
      Accés obert
      n preparation of the forthcoming high power campaign with the reactor-relevant deuterium-tritium (DT) fuel mixture in the Joint European Torus (JET), significant efforts are being devoted to DT scenario extrapolation using ...

    • Hacia la monitorización dinámica del inventario de tritio en los sistemas auxiliares de un reactor de fusión 

      Batet Miracle, Lluís; Iraola de Acevedo, Eduardo; Sedano Miguel, Luis Ángel; Nougués, José María (2019)
      Comunicació de congrés
      Accés restringit per política de l'editorial
      La sostenibilidad de la fusión nuclear depende, entre otros condicionantes, de la capacidad de regeneración de tritio. Los requisitos de protección radiológica imponen severas limitaciones a las emisiones ambientales de ...

    • Implementation of two-phase tritium models for helium bubbles in HCLL breeding blanket modules 

      Fradera, Jordi; Sedano, L.A.; Mas de les Valls Ortiz, Elisabet; Batet Miracle, Lluís (2011)
      Article
      Accés restringit per política de l'editorial
      Tritium self-sufficiency requirement of future DT fusion reactors involves large helium production rates in the breeding blankets; this might impact on the conceptual design of diverse fusion power reactor units, such ...

    • ITER Loss of Plasma Control Transients Analysis 

      Prior Miqueo, Claudia (Universitat Politècnica de Catalunya, 2014-05)
      Projecte/Treball Final de Carrera
      Accés obert
      En el presente informe se realiza un estudio de transitorios de pérdida de control del plasma en ITER. Para la realización del estudio se ha utilizado AINA 3.0, un código de seguridad desarrollado por Fusion Energy ...

    • Linear scaling DFT calculations for large tungsten systems using an optimized local basis 

      Mohr, Stephan; Eixarch, Marc; Amsler, Maximilian; Mantsinen, Mervi J.; Genovese, Luigi (Elsevier, 2018-05)
      Article
      Accés obert
      Density functional theory (DFT) has become a standard tool for ab-initio simulations for a wide range of applications. While the intrinsic cubic scaling of DFT was for a long time limiting the accessible system size to ...

    • Methodological guide to deploy Functional Analysis into CODAC Systems for the Tritium Processing in ITER 

      Granados Granados, Ricardo Jose (Universitat Politècnica de Catalunya, 2018-06-21)
      Projecte Final de Màster Oficial
      Accés obert
      The present document is focused on the a nalysis of the ITER - TBM‘s Proto - CODAC system. ITER is considered to be the first nuclear fusion reactor to be energetically feasible for a sustained period of time with a rated ...

    • MHD para fusión: parámetros puente entre CFD y códigos de sistema 

      Mas de les Valls Ortiz, Elisabet; Batet Miracle, Lluís; Sedano, L.A. (2012)
      Comunicació de congrés
      Accés restringit per política de l'editorial

    • Modelat del transport de triti en un canal de l'embolcall regenerador de triti d'un reactor de fusió DT 

      Bermúdez García, Pau (Universitat Politècnica de Catalunya, 2010-12)
      Projecte/Treball Final de Carrera
      Accés obert
      El projecte que es presenta té com a principal objectiu presentar un model per al transport de triti d’un canal d’un embolcall regenerador (embolcall tritigeni) d’un reactor de fusió D-T. El model pot ser una eina molt ...

    • Modeling the Tokamak exhaust processing system in a commercial simulator for process monitoring purposes 

      Iraola de Acevedo, Eduardo; Nougués, José María; Batet Miracle, Lluís; Feliu, Josep Anton; Sedano, Luis (Taylor & Francis Group, 2023-10-24)
      Article
      Accés restringit per política de l'editorial
      Nuclear fusion depends on tritium breeding and self-sufficiency. Tritium represents a hazard due to its radioactivity and migration properties. Because of these difficulties, ITER, the largest fusion experiment so far, ...

    • Nucleation of helium in liquid lithium at 843 K and high pressures 

      Martí Rabassa, Jordi; Mazzanti Castrillejo, Fernando Pablo; Astrakharchik, Grigori; Batet Miracle, Lluís; Portos-Amill, Laura; Pedreño, Borja (Multidisciplinary Digital Publishing Institute (MDPI), 2022-04-13)
      Article
      Accés obert
      Fusion energy stands out as a promising alternative for a future decarbonised energy system. In order to be sustainable, future fusion nuclear reactors will have to produce their own tritium. In the so-called breeding ...

    • Nucleation of helium in pure liquid lithium 

      Álvarez Galera, Edgar; Martí Rabassa, Jordi; Mazzanti Castrillejo, Fernando Pablo; Batet Miracle, Lluís (American Institute of Physics (AIP), 2023-07-14)
      Article
      Accés obert
      Tritium self-sufficiency in fusion nuclear reactors will be based on the neutron capture by lithium in the so-called breeding blankets of the reactor, a nuclear reaction that will produce helium along with tritium. The low ...

    • Numerical analysis of MHD-thermofluid flows considering sandwich structures as applied to liquid breeding blankets for fusion technology 

      Mas de les Valls Ortiz, Elisabet; Batet Miracle, Lluís; Medina Iglesias, Vicente César de; Fradera, Jordi; Sedano, L.A. (2011)
      Text en actes de congrés
      Accés restringit per política de l'editorial
      Lead lithium flowing inside breeding blanket’s channels in a fusion reactor is subject to a Hartmann number of 104 and a Grashof number 109􀀀12. Since under such conditions buoyancy can be of the same order of magnitude ...

    • Overview of JET results for optimising ITER operation 

      Mailloux, Joelle; Abid, N.; Abraham, K.; Abreu, Paulo; Adabonyan, O.; Adrich, P.; Gadariya, G.; Gallart Escolà, Daniel; Manyer Fuertes, Jordi; Mantsinen, Mervi Johanna (2022)
      Article
      Accés obert
      The JET 2019–2020 scientific and technological programme exploited the results of years of concerted scientific and engineering work, including the ITER-like wall (ILW: Be wall and W divertor) installed in 2010, improved ...

    • Overview of the JET results in support to ITER 

      Litaudon, Xavier; Abduallev, Sadrilla; Abhangi, Mitul; Abreu, Paulo; Afza, M.; Aggarwa, K. M.; Ahlgren, Tommy; Ahn, Jae Heon; Aho-Mantila, Leena; Aiba, Nobuyuki; Futatani, Shimpei; Gallart Escolà, Daniel; Mantsinen, Mervi Johanna; Rakha, Allah (Institute of Physics (IOP), 2017-06-15)
      Article
      Accés obert
      The 2014–2016 JET results are reviewed in the light of their significance for optimising the ITER research plan for the active and non-active operation. More than 60 h of plasma operation with ITER first wall materials ...

    • Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development 

      Stroth, Ulrich; Aguiam, Diogo; Alessi, Edoardo; Angioni, Clemente; Arden, Nils; Futatani, Shimpei; Gallart Escolà, Daniel; Mantsinen, Mervi (IOP Publishing, 2022-03)
      Article
      Accés obert
      An overview of recent results obtained at the tokamak ASDEX Upgrade (AUG) is given. A work flow for predictive profile modelling of AUG discharges was established which is able to reproduce experimental H-mode plasma ...

    • Progress with applications of three-ion ICRF scenarios for fusion research: A review 

      Kazakov, Ye O.; Ongena, J.; Nocente, M.; Bobkov, Volodymyr; Garcia, J.; Gallart, Daniel; Mantsinen, Mervi J. (American Institute of Physics Publishing, 2023)
      Article
      Accés obert
      The viability of magnetic confinement fusion as an energy source depends on achieving the high ion temperatures required for D-T fusion. Among the available techniques, plasma heating with waves in the ion cyclotron range ...