Publications (43) Nerea Ordas Mur publications

2024

  1. On the feasibility to obtain CuCrZr alloys with outstanding thermal and mechanical properties by additive manufacturing

    Journal of Nuclear Materials, Vol. 601

2023

  1. Development Of Nickel Aluminium Bronzes By Powder Metallurgy For Marine Applications

    Euro Powder Metallurgy 2023 Congress and Exhibition, PM 2023

  2. Laser-Directed Energy Deposition Processing As A Tool To Repair Or Obtain Hybrid Complex-Shape Components

    Euro Powder Metallurgy 2023 Congress and Exhibition, PM 2023

2022

  1. Towards The Uspcaling Of ODS Steels: STARS ROUTE®

    World PM 2022 Congress Proceedings

2021

  1. Development of CuCrZr via Electron Beam Powder Bed Fusion (EB-PBF)

    Journal of Nuclear Materials, Vol. 548

  2. Super Duplex Stainless Steels obtained by PM-HIP

    Euro PM2021 Congress Proceedings

2020

  1. Role of hip parameters and thermo-mechanical treatments on ODS ferritic steels obtained with the Stars route

    Euro PM 2018 Congress and Exhibition

2019

  1. Deuterium retention in tungsten based materials for fusion applications

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

  2. Microstructural comparison of Oxide Dispersion Strengthened Fe-14Cr steels produced by HIP and SPS

    Fusion Engineering and Design, Vol. 146, pp. 2328-2333

  3. The Quality of Fe14Cr ODS Powder Alloys During Milling and Upon Heating and Its Impact on the Mechanical Properties of Consolidated Steels

    Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science, Vol. 50, Núm. 7, pp. 3282-3294

2018

  1. A comparison of the structure and mechanical properties of commercially pure tungsten rolled plates for the target of the European spallation source

    International Journal of Refractory Metals and Hard Materials, Vol. 70, pp. 45-55

  2. ODS ferritic steels obtained from gas atomized powders through the STARS processing route: Reactive synthesis as an alternative to mechanical alloying

    Nuclear Materials and Energy, Vol. 17, pp. 1-8

  3. 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

  4. The role of yttrium and titanium during the development of ODS ferritic steels obtained through the STARS route: TEM and XAS study

    Journal of Nuclear Materials, Vol. 504, pp. 8-22

  5. XPS and SEM analysis of the surface of gas atomized powder precursor of ODS ferritic steels obtained through the STARS route

    Applied Surface Science, Vol. 427, pp. 182-191

2017

  1. Mechanical and microstructural characterization of HIP joints of a simplified prototype of the ITER NHF First Wall Panel

    Fusion Engineering and Design, Vol. 124, pp. 999-1003

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

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

  3. Smart alloys for a future fusion power plant: First studies under stationary plasma load and in accidental conditions

    Nuclear Materials and Energy, Vol. 12, pp. 1363-1367

  4. Smart tungsten alloys as a material for the first wall of a future fusion power plant

    Nuclear Fusion, Vol. 57, Núm. 6

2016

  1. Fracture strength testing of a self-passivating tungsten alloy at the micrometre scale

    Philosophical Magazine, Vol. 96, Núm. 32-34, pp. 3570-3585