Publicaciones en colaboración con investigadores/as de Max Planck Institute of Plasma Physics (61)

2024

  1. Mock-ups fabrication by HRP technology with advanced W-alloy monoblocks for DEMO divertor target

    Fusion Engineering and Design, Vol. 201

2020

  1. Microstructure, oxidation behaviour and thermal shock resistance of self-passivating W-Cr-Y-Zr alloys

    Nuclear Materials and Energy, Vol. 24

2019

  1. Deuterium retention in tungsten based materials for fusion applications

    Nuclear Materials and Energy, Vol. 18, pp. 245-249

2018

  1. Self-passivating tungsten alloys of the system W-Cr-Y for high temperature applications

    International Journal of Refractory Metals and Hard Materials, Vol. 73, pp. 29-37

2017

  1. Advanced materials for a damage resilient divertor concept for DEMO: Powder-metallurgical tungsten-fibre reinforced tungsten

    Fusion Engineering and Design, Vol. 124, pp. 964-968

  2. Self-passivating W-Cr-Y alloys: Characterization and testing

    Fusion Engineering and Design, Vol. 124, pp. 1118-1121

2016

  1. Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants

    Fusion Engineering and Design, Vol. 109-111, pp. 1046-1052

  2. Manufacturing and testing of self-passivating tungsten alloys of different composition

    Nuclear Materials and Energy, Vol. 9, pp. 422-429

2014

  1. Oxidation behaviour of bulk W-Cr-Ti alloys prepared by mechanical alloying and HIPing

    Fusion Engineering and Design

2013

  1. A brief summary of the progress on the EFDA tungsten materials program

    Journal of Nuclear Materials, Vol. 442, Núm. 1-3 SUPPL.1

  2. Powder metallurgical processing of self-passivating tungsten alloys for fusion first wall application

    Journal of Nuclear Materials, Vol. 442, Núm. 1-3 SUPPL.1

  3. Recent progress in R&D on tungsten alloys for divertor structural and plasma facing materials

    Journal of Nuclear Materials, Vol. 442, Núm. 1-3 SUPPL.1

  4. Recent progress in research on tungsten materials for nuclear fusion applications in Europe

    Journal of Nuclear Materials, Vol. 432, Núm. 1-3, pp. 482-500

2012

  1. Self-passivating tungsten based alloys obtained by hip for application in fusion reactors beyond ITER (Demo)

    Proceedings of the International Euro Powder Metallurgy Congress and Exhibition, Euro PM 2012

2011

  1. Compilation of erosion yields of metal-doped carbon materials by deuterium impact from ion beam and low temperature plasma

    Journal of Nuclear Materials

  2. Manufacturing of self-passivating W-Cr-Si alloys by mechanical alloying and HIP

    Fusion Engineering and Design, Vol. 86, Núm. 9-11, pp. 1719-1723

  3. Review on the EFDA programme on tungsten materials technology and science

    Journal of Nuclear Materials

  4. Self-passivating bulk tungsten-based alloys manufactured by powder metallurgy

    Physica Scripta T

2009

  1. Improvement of thermal shock resistance of isotropic graphite by Ti-doping

    Journal of Nuclear Materials, Vol. 386-388, Núm. C, pp. 805-808

  2. Ti-doped isotropic graphite: A promising armour material for plasma-facing components

    Journal of Nuclear Materials, Vol. 386-388, Núm. C, pp. 801-804