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Fusion engineering and design

Total activitats: 33
Títol addicional
ScienceDirect e-journals
ISSN
0920-3796 Obrir en finestra nova
Publicació / Producció
New York, NY : Elsevier Science Pub. Co., [199?]-
URL
https://www.sciencedirect.com/science/journal/09203796 Obrir en finestra nova

Producció científica

1 a 33 de 33 resultats
 
  • Methodology for the improvement of the AINA code wall-modelapplied to DEMO WCPB blanket

     Fabbri, M.; de Blas, A.; Riego, A.; Dies, J.; Zamora, I.; Baeza, E.
    Fusion engineering and design
    DOI: 10.1016/j.fusengdes.2017.05.027
    Data de publicació: 2017-05-29
    Article en revista
  • Distribution of the In-Vessel Diagnostics in ITER Tokamak

     Gonzalez, J.; Clough, M.; Martin, A.; Woods, N.; Suarez, A.; Martinez, G.; Gicquel, S.; Yunxing, M.
    Fusion engineering and design
    Vol. 114, p. 180-186
    DOI: 10.1016/j.fusengdes.2016.12.009
    Data de publicació: 2017-01-01
    Article en revista
  • Effect on the tritium breeding ratio due to a distributed ICRF antenna in a DEMO reactor

     García, Ángela; Noterdaeme, J.; Fischer, U.; Dies, J.
    Fusion engineering and design
    Vol. 112, p. 298-302
    DOI: 10.1016/j.fusengdes.2016.08.028
    Data de publicació: 2016-11-15
    Article en revista
  • Safety studies of plasma-wall events with AINA code for Japanese DEMO

     Rivas, J.; Dies, J.; Fabbri, M.; Nakamura, M.
    Fusion engineering and design
    Vol. 109, p. 1653-1657
    DOI: 10.1016/j.fusengdes.2015.10.037
    Data de publicació: 2016-11-01
    Article en revista
  • An approach to verification and validation of MHD codes for fusion applications

     Smolentsev, S.; Badia, S.; Bhattacharyayd, R.; Mas de les Valls, E.; Patel, A.
    Fusion engineering and design
    Vol. 100, num. 11/2015, p. 65-72
    DOI: 10.1016/j.fusengdes.2014.04.049
    Data de publicació: 2015-11
    Article en revista
  • Revisiting the analysis of passive plasma shutdown during an ex-vessel loss of coolant accident in ITER blanket

     Rivas, J.C.; Dies, J.; Fajarnes, X.
    Fusion engineering and design
    Vol. 98-99, p. 2206-2209
    DOI: 10.1016/j.fusengdes.2015.06.143
    Data de publicació: 2015-10-01
    Article en revista
  • Results of the RAMI analyses performed for the IFMIF accelerator facility in the engineering design phase  Accés obert

     Bargalló, E.; Arroyo, J.; Abal, J.; Dies, J.; de Blas, A.; Tapia, C.; Moya, J.; Ibarra, A.
    Fusion engineering and design
    Vol. 98-99, p. 1933-1936
    DOI: 10.1016/j.fusengdes.2015.06.011
    Data de publicació: 2015-10-01
    Article en revista
    Accés al text complet
  • Diagnostic integration solutions in the ITER first wall

     Martinez, G.; Martin, A.; Watts, C.; Veshchev, E.; Reichle, R.; Shigin, P.; Sabourin, F.; Gicquel, S.; Mitteau, R.; González, J.
    Fusion engineering and design
    Vol. 98-99, p. 1548-1551
    DOI: 10.1016/j.fusengdes.2015.06.046
    Data de publicació: 2015-10-01
    Article en revista
  • Mathematical models for tritium permeation analysis in liquid metal flows with helium bubbles

     Batet, L.; Mas de les Valls, E.; Sedano, L.
    Fusion engineering and design
    Vol. 89, num. 7-8, p. 1158-1162
    DOI: 10.1016/j.fusengdes.2014.04.031
    Data de publicació: 2014-10-01
    Article en revista
  • ITER safety studies: the effect of two simultaneous perturbations during a loss of plasma control transient

     Rivas, J.C.; Dies, J.
    Fusion engineering and design
    Vol. 89, num. 9-10, p. 2043-2047
    DOI: 10.1016/j.fusengdes.2014.04.010
    Data de publicació: 2014-10-01
    Article en revista
  • Availability simulation software adaptation to the IFMIF accelerator facility RAMI analyses

     Bargalló, E.; Sureda, P.; Arroyo, J.; Abal, J.; de Blas, A.; Dies, J.; Tapia, C.; Mollá, J.; Ibarra, A.
    Fusion engineering and design
    Vol. 89, num. 9-10, p. 2425-2429
    DOI: 10.1016/j.fusengdes.2013.12.004
    Data de publicació: 2014-10-01
    Article en revista
  • Modelling of a supercritical CO2 power cycle for nuclear fusion reactors using RELAP5-3D

     Batet, L.; Álvarez-Fernández, J.M.; Mas de les Valls, E.; Martinez, V.; Perez, M.; Reventos, F.; Sedano, L.
    Fusion engineering and design
    Vol. 89, num. 4, p. 354-359
    DOI: 10.1016/j.fusengdes.2014.03.018
    Data de publicació: 2014-04-01
    Article en revista
  • Hardware availability calculations and results of the IFMIF accelerator facility

     Bargalló, E.; Arroyo, J.; Abal, J.; Podadera, I.; de Blas, A.; Dies, J.; Tapia, C.; Mollá, J.
    Fusion engineering and design
    Vol. 89, num. 9-10, p. 2388-2392
    DOI: 10.1016/j.fusengdes.2014.01.030
    Data de publicació: 2014-02-22
    Article en revista
  • Detailed mechanical design of the LIPAc beam dump radiological shielding

     Nomen, O.; Mollá, J.; Sanmartí, M.; Martínez, J.I.; Arranz , F.; Iglesias, D.; Barrera, G.; Brañas, B.; Ogando, F.
    Fusion engineering and design
    Vol. 88, num. 9-10, p. 2723-2727
    DOI: 10.1016/j.fusengdes.2013.01.105
    Data de publicació: 2013-10-02
    Article en revista
  • RAMI strategies in the IFMIF Test Facilities design

     Abal, J.; Dies, J.; Bargalló, E.; Tapia, C.; de Blas, A.
    Fusion engineering and design
    Vol. 88, num. 9-10, p. 2535-2538
    DOI: 10.1016/j.fusengdes.2013.04.003
    Data de publicació: 2013-10-01
    Article en revista
  • Safety studies: Review of loss of plasma control transients in ITER with AINA 3.0 Code

     Rivas, J.C.; Dies, J.
    Fusion engineering and design
    Vol. 88, num. 9-10, p. 2709-2713
    Data de publicació: 2013-10
    Article en revista
  • Availability, reliability and logistic support studies of the RF power system design options for the IFMIF accelerator

     Bargalló, E.; Giralt, A.; Martinez, G.; Weber, M.; Regidor, D.; Arroyo, J.; Abal, J.; Dies, J.; Tapia, C.; de Blas, A.; Mendez, P.; Ibarra, A.; Mollá, J.
    Fusion engineering and design
    DOI: 10.1016/j.fusengdes.2013.01.016
    Data de publicació: 2013-01
    Article en revista
  • Present status of the Liquid Breeder Validation Module for IFMIF

     Casal, N.; Mas, A.; Mota, F.; García, Ángela; Nomen, O.; Rapisarda, D.; Arroyo, J.; Abal, J.; Mollá, J.; Ibarra, A.
    Fusion engineering and design
    Vol. 88, num. 6-8, p. 863-867
    DOI: 10.1016/j.fusengdes.2013.03.057
    Data de publicació: 2013
    Article en revista
  • RAMI analyses of the IFMIF accelerator facility and first availability allocation between systems

     Bargalló, E.; Abal, J.; Dies, J.; Tapia, C.; de Blas, A.
    Fusion engineering and design
    Vol. 88, num. 9-10, p. 2728-2731
    DOI: 10.1016/j.fusengdes.2012.11.014
    Data de publicació: 2012-12
    Article en revista
  • Influence of thermal performance on design parameters of a He/LiPb dual coolant DEMO concept blanket design

     Mas de les Valls, E.; Batet, L.; De Medina, V.; Fradera, J.; Sanmartí, M.; Sedano, L.
    Fusion engineering and design
    Vol. 87, num. 7-8, p. 969-973
    DOI: 10.1016/j.fusengdes.2012.02.074
    Data de publicació: 2012-08
    Article en revista
  • IFMIF accelerator: database, FMEA, fault tree and RAM

     Tapia, C.; Dies, J.; Pesudo, V.; Abal, J.; Ibarra, A.; Arroyo, J.
    Fusion engineering and design
    Vol. 86, num. 9-11, p. 2722-2725
    DOI: 10.1016/j.fusengdes.2011.02.099
    Data de publicació: 2011-10
    Article en revista
  • Design and qualification of an on-line permeator for the recovery of tritium from lead-lithium eutectic breeding alloy

     Veredas, G.; Fradera, J.; Fernández, I.; Batet, L.; Peñalva, I.; Mesquida, L.; Abell, J.; Sempere, J.; Martínez, I.; Herrazti, B.; Sedano, L.
    Fusion engineering and design
    Vol. 86, num. 9-11, p. 2365-2369
    DOI: 10.1016/j.fusengdes.2011.03.077
    Data de publicació: 2011-10
    Article en revista
  • Exploration of reliability databases and comparison of former IFMIF's results

     Tapia, C.; Dies, J.; Abal, J.; Ibarra, A.; Arroyo, J.
    Fusion engineering and design
    Vol. 86, num. 9-11, p. 2726-2729
    DOI: 10.1016/j.fusengdes.2010.12.078
    Data de publicació: 2011-10
    Article en revista
  • Qualification of MHD effects in dual-coolant DEMO blanket and approaches to their modelling

     Mas de les Valls, E.; Batet, L.; De Medina, V.; Fradera, J.; Sedano, L.
    Fusion engineering and design
    Vol. 86, num. 9-11, p. 583-589
    DOI: 10.1016/j.fusengdes.2011.03.071
    Data de publicació: 2011-10
    Article en revista
  • Numeric implementation of a nucleation, growth and transport model for helium bubbles in lead–lithium HCLL breeding blanket channels: Theory and code development

     Batet, L.; Fradera, J.; Mas de les Valls, E.; Sedano, L.
    Fusion engineering and design
    Vol. 86, num. 4-5, p. 421-428
    DOI: 10.1016/j.fusengdes.2011.03.074
    Data de publicació: 2011-06
    Article en revista
  • Modelling of integrated effect of volumetric heating and magnetic field on tritium transport in a U-bend flow as applied to HCLL blanket concept

     Mas de les Valls, E.; Batet, L.; De Medina, V.; Fradera, J.; Sedano, L.
    Fusion engineering and design
    Vol. 86, num. 4-5, p. 341-356
    DOI: 10.1016/j.fusengdes.2011.02.075
    Data de publicació: 2011
    Article en revista
  • Developing the IFMIF RAM planning

     Tapia, C.; Dies, J.; Calvo, A.; Rivas, J.C.; Ibarra, A.
    Fusion engineering and design
    Vol. 84, num. 7-11, p. 1823-1826
    DOI: 10.1016/j.fusengdes.2009.02.025
    Data de publicació: 2009-06
    Article en revista
  • Reliability of the TJ-II power supply system: Collection and analysis of the operational experience data

     Izquierdo, J.; Dies, J.; Garcia, J.; Tapia, C.; Alonso, J.; Ascasibar, E.; Medrano, M.; Mendez, P.; Rodriguez, L.
    Fusion engineering and design
    Vol. 82, num. 15-24, p. 2765-2771
    Data de publicació: 2007-10
    Article en revista
  • Safety assessment of energy fluxes on in-vessel components with SAFALY

     Izquierdo, J.; Dies, J.; Garcia, J.; Tapia, C.; Cortes, G.; Rodriguez, L.
    Fusion engineering and design
    Vol. 82, num. 15-24, p. 2856-2860
    Data de publicació: 2007-10
    Article en revista
  • Burning plasmas simulation of TR-1 tokamak and HR-1 helical reactors

     Yamazaki, K.; Dies, J.; Igitkhanov, Y.
    Fusion engineering and design
    Vol. 81, num. 23-24, p. 2743-2748
    Data de publicació: 2006-01
    Article en revista
  • Fusion component failure rate database (FCFR-DB)

     Pinna, T.; Izquierdo, J.; Porfiri, M.; Dies, J.
    Fusion engineering and design
    num. 81, p. 1391-1395
    Data de publicació: 2006-01
    Article en revista
  • Progress in the development of a PIE-PIT for the ITER Tokamak

     Izquierdo, J.; Taylor, N.; Dies, J.; Garcia, J.; Albajar, F.
    Fusion engineering and design
    Vol. 75-79, p. 1145-1149
    Data de publicació: 2005-11
    Article en revista
  • Software and hardware developments for remote participation in TJ-II operation . Proof of concept using the NPA diagnostic

     Lopez, A.; Vega, J.; Montoro, A.; Sanchez, E.; Encabo, J.; Portas, A.; Balbin, R.; Fontdecaba, J.; Jimenez, J.; Dies, J.; Tj-Ii, T.
    Fusion engineering and design
    Vol. 60, p. 487-492
    Data de publicació: 2002-01
    Article en revista