M. Roldán

ORCID: 0000-0003-1695-2199
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About
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Research Areas
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Metal and Thin Film Mechanics
  • Additive Manufacturing Materials and Processes
  • Ion-surface interactions and analysis
  • Welding Techniques and Residual Stresses
  • Microstructure and Mechanical Properties of Steels
  • Microstructure and mechanical properties
  • Diamond and Carbon-based Materials Research
  • Advanced materials and composites
  • Advanced Welding Techniques Analysis
  • Material Properties and Applications
  • Hydrogen embrittlement and corrosion behaviors in metals
  • Nuclear Physics and Applications
  • Theoretical and Computational Physics
  • High Temperature Alloys and Creep
  • Quantum Dots Synthesis And Properties
  • Aluminum Alloy Microstructure Properties
  • Magnetic Properties and Applications
  • ZnO doping and properties
  • Metallurgical Processes and Thermodynamics
  • High Entropy Alloys Studies
  • Silicon and Solar Cell Technologies
  • Complex Network Analysis Techniques
  • Nuclear materials and radiation effects

Universidad Complutense de Madrid
2014-2024

Centro de Investigaciones Energéticas, Medioambientales y Tecnológicas
2014-2024

Universidad Autónoma de Madrid
2021-2022

Universidad Rey Juan Carlos
2018

Fusion for Energy
2016

Additively manufactured AISI 316 L stainless steel samples were heat treated at temperatures from 400 °C to 1100 °C, and the corrosion behavior in chloride environments was electrochemically studied. Heat treatments 650 increased grain size treatment formed MnCr2O4 inclusions. Also, these postprocessing techniques reduce hardness porosity. polarization resistance maintained pitting mechanisms of additively samples. higher reduced but changed mechanisms.

10.1016/j.corsci.2022.110777 article EN cc-by-nc-nd Corrosion Science 2022-10-21

For improved performance of the components in a fusion reactor, an increased application temperature for structural materials such as 9%Cr reduced activation steels is crucial. The improvement current generation (i.e. EUROFER) one aims EUROfusion programme advanced steels. goal this work to determine most effective thermo-mechanical treatment ferritic martensitic with respect high-temperature strength. Compatibility these treatments industrial production processes essential. In present...

10.1016/j.nme.2015.12.001 article EN cc-by-nc-nd Nuclear Materials and Energy 2016-01-01

Abstract There is no doubt about the interest of achieving as fast possible capability to build and operate high performance reactors that finally allow fusion competing in electricity market. An advanced breeding blanket based on Dual Coolant Lithium Lead concept with single module segment architecture, designed for European DEMO, certainly aligned such objective. This work describes some recent outcomes efforts carried out framework Prospective R&D Work Package EUROfusion develop this...

10.1088/1741-4326/ad37ca article EN cc-by Nuclear Fusion 2024-03-26

Copper nitride (Cu3N) has gained significant attention recently due to its potential in several scientific and technological applications. This study focuses on using Cu3N as a solar absorber photovoltaic technology. thin films were deposited glass substrates silicon wafers via radio-frequency magnetron sputtering at different nitrogen flow ratios with total pressures ranging from 1.0 5.0 Pa. The films’ structural, morphology, chemical properties determined XRD, Raman, AFM, SEM/EDS...

10.3390/coatings13061094 article EN Coatings 2023-06-13

This work aims to fill a gap in the H transport database for niobium and vanadium, materials proposed fabrication of tritium extraction systems. The permeability, key parameter this application, has not been properly determined so far. Values are given H2 D2 permeability two different Nb samples from suppliers but with similar microstructure ∼300 °C 500 tested loading pressures 20 mbar mbar: ϕ(Nb/H2)[mol·m−1·s−1·Pa−0.5]=4.49·exp(−19,258T)ϕ(Nb/D2)[mol·m−1·s−1·Pa−0.5]=1.31·exp(−19,332T)For new...

10.1016/j.jnucmat.2024.155142 article EN cc-by-nc Journal of Nuclear Materials 2024-04-30

The brazeability of a cupronickel commercial alloy (Cu10Ni) was evaluated for its use as filler high-temperature joining tungsten to the reduced activation ferritic/martensitic steel EUROFER 97 (W-E) and between base materials (W-W) application at first wall divertor future fusion reactors. In addition, given importance residual stresses in these heterogenous joints, study brazing conditions impact selected has been conducted using numerical software understand on quality joint. Two thermal...

10.1016/j.jnucmat.2023.154830 article EN cc-by Journal of Nuclear Materials 2023-11-22

The effect of post-helium irradiation annealing on bubbles and nanoindentation hardness two reduced activation ferritic martensitic steels for nuclear fusion applications (EUROFER97 EU-ODS EUROFER) has been studied. Helium-irradiated EUROFER97 EUROFER were annealed at 450 °C 100 h in an argon atmosphere. samples tested by studied transmission electron microscopy extracting some focused ion beam lamellae containing the whole implanted zone (≈50 µm). A substantial increment was measured area...

10.3390/mi9120633 article EN cc-by Micromachines 2018-11-29

In this article, a preliminary microscale study of brazed joint two materials that will conform the future fusion reactors is carried out. Tungsten act as plasma-facing material attached to structure made some reduced activation ferritic-martensitic steel (Eurofer-like steel). The proposed brazing process introduces copper filler and develops thermal in high vacuum atmosphere at 1135 °C for 10 min. resultant microstructure characterised by forming diffusion layer contact with tungsten base...

10.1016/j.nme.2022.101155 article EN cc-by Nuclear Materials and Energy 2022-02-26

Neutron induced damage in future nuclear materials can be studied using heavy ion beams only if the differences microstructure evolution are well understood. Large variations dose rate, caused by scanning of beam, alter compared to steady-state irradiation. We study effect on irradiating pure iron with a 10 MeV Fe beam 0.2 dpa. The is scanned one direction frequencies 200 Hz and kHz. Different shapes also used variation. All irradiations conducted at room temperature DiFU chamber RBI. TEM...

10.1016/j.nme.2024.101628 article EN cc-by Nuclear Materials and Energy 2024-03-01

Small specimen testing technology (SSTT) refers to the examination of tiny samples materials evaluate their suitability for use in fusion reactors. This includes assessing thermal, mechanical, and radiation properties, as well ability withstand extreme conditions. SSTT plays a critical role development nuclear technology, which holds potential provide virtually limitless clean energy source. is imperative cases where not much material available or must be subjected special conditions that...

10.1016/j.nme.2024.101679 article EN cc-by-nc-nd Nuclear Materials and Energy 2024-05-18

The CuCrZr alloy combines high thermal conductivity and mechanical strength with stability at high-medium temperatures, making it a promising heat sink material for the EU-DEMO divertor limiters. Additive Manufacturing (AM) technologies have proven effective in developing complex-shaped components almost no constraints on geometry minimal machining welding requirements. This makes them particularly suitable production of exchangers featuring complex cooling channels intricate inner...

10.1016/j.jnucmat.2024.155304 article EN cc-by-nc Journal of Nuclear Materials 2024-07-28

RAFM steels EUROFER97 and EU-ODS EUROFER samples have been implanted with He ions at 40 keV (ion penetration depth ~300 nm) a dose of ~ 1 × 1015 ion/cm2 different temperatures up to 550 °C. Post-irradiation examination the has performed using nanoindentation along conventional scanning transmission electron microscopy (CTEM/STEM in Annular Dark Field mode). The specimens were indented 500 nm by CSM method (Continuous Stiffness Measurement), order assess changes hardness values due...

10.1016/j.nme.2019.100717 article EN cc-by Nuclear Materials and Energy 2019-11-20

In the present investigation, high-energy self-ion irradiation experiments (20 MeV Fe+4) were performed on two types of pure Fe samples to evaluate formation dislocation loops as a function material volume. The choice model material, namely EFDA Fe, was made emulate simulated with computational models that study defect evolution. experimental conditions an ion fluence 4.25 and 8.5 × 1015 ions/cm2 temperature 350 450 °C, respectively. First, ions pass through samples, which are thin films...

10.3390/met11122000 article EN cc-by Metals 2021-12-10

The mechanical behaviour of prismatic bars extracted from a high purity alumina tube was studied comparatively in the as-received condition and after being irradiated with high-energy protons. For this study, ten samples were 8 MeV H+ ion beams up to fluence 1.63 × 1016 ions/cm2. Values compressive strength, elastic modulus, hardness, fracture toughness determined compression micro-indentation tests. After tests, relationship shown microstructure considered by scanning electron microscopy...

10.1016/j.nme.2022.101173 article EN cc-by-nc-nd Nuclear Materials and Energy 2022-03-23
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