Ł. Ciupiński

ORCID: 0000-0002-4536-3177
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About
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Research Areas
  • Fusion materials and technologies
  • Nuclear Materials and Properties
  • Advanced materials and composites
  • Ion-surface interactions and analysis
  • Advanced Thermoelectric Materials and Devices
  • Magnetic confinement fusion research
  • Advanced ceramic materials synthesis
  • Intermetallics and Advanced Alloy Properties
  • Aluminum Alloys Composites Properties
  • Diamond and Carbon-based Materials Research
  • Superconducting Materials and Applications
  • Advanced Materials Characterization Techniques
  • Metal and Thin Film Mechanics
  • Chalcogenide Semiconductor Thin Films
  • Welding Techniques and Residual Stresses
  • Powder Metallurgy Techniques and Materials
  • Particle accelerators and beam dynamics
  • Microstructure and mechanical properties
  • Nuclear materials and radiation effects
  • Tunneling and Rock Mechanics
  • Cultural Heritage Materials Analysis
  • Nuclear Physics and Applications
  • Nuclear reactor physics and engineering
  • Thermal properties of materials
  • Injection Molding Process and Properties

Warsaw University of Technology
2016-2025

KTH Royal Institute of Technology
2020

AGH University of Krakow
2017

Wrocław University of Science and Technology
2017

Institute of Electronic Materials Technology
2017

Materials Science & Engineering
2014

Forschungszentrum Jülich
2011

The provision of a particle and power exhaust solution which is compatible with first-wall components edge-plasma conditions key area present-day fusion research mandatory for successful operation ITER DEMO. work package plasma-facing (WP PFC) within the European programme complements laboratory experiments, i.e. in linear plasma devices, electron ion beam loading facilities, studies performed toroidally confined magnetic such as JET, ASDEX Upgrade, WEST etc. connection both groups done via...

10.1088/1741-4326/aa796e article EN cc-by Nuclear Fusion 2017-06-14

The next step in the Wendelstein stellarator line is large superconducting device 7-X, currently under construction Greifswald, Germany. Steady-state operation an intrinsic feature of stellarators, and one key element 7-X mission to demonstrate steady-state plasma conditions relevant for a fusion power plant. device, on hand, requires implementation special technologies, giving rise technical challenges during design, fabrication assembly such device. On other also physics development at...

10.1088/0029-5515/53/12/126001 article EN Nuclear Fusion 2013-11-13

The thermal diffusivity (TD) and conductivity (TC) of Cu–Cr–diamond composite materials were examined in the temperature range from 50 to 300 °C for diamond volume fractions 22, 40, 50, 55, 60 %. samples fabricated by plasma pulse sintering (PPS) method. TC does not increase proportionally with fraction particular materials. highest TD was determined % fraction, evaluated reached 658 W m−1 K−1 at °C. This article complements earlier articles concerning synthesis characterization...

10.1007/s10973-013-3604-3 article EN cc-by Journal of Thermal Analysis and Calorimetry 2014-01-29

10.1016/j.nimb.2013.03.022 article EN Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms 2013-03-29

Abstract Antimony telluride (Sb 2 Te 3 ) is an intermetallic compound crystallizing in a hexagonal lattice with R-3m space group. It creates c lose packed structure of ABCABC type. As intrinsic semiconductor characterized by excellent electrical properties, Sb widely used as low-temperature thermoelectric material. At the same time, due to unusual properties (strictly connected structure), antimony exhibits nonlinear optical including saturable absorption. Nanostructurization, elemental...

10.1515/amm-2017-0155 article EN cc-by-nc Archives of Metallurgy and Materials 2017-06-01

10.1016/j.nimb.2014.07.043 article EN Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms 2014-09-02

Results are presented for the dust survey performed at JET after second experimental campaign with ITER-Like Wall: 2013–2014. Samples were collected on adhesive stickers from several different positions in divertor both tiles and carrier. Brittle dust-forming deposits test mirrors inner wall also studied. Comprehensive characterization accomplished by a wide range of high-resolution microscopy techniques, including focused ion beam, has led to identification classes particles: (i) beryllium...

10.1016/j.nme.2016.11.027 article EN cc-by-nc-nd Nuclear Materials and Energy 2017-01-28

The influence of the annealing temperature on deuterium retention was studied for self-ion damaged tungsten in range from 600–1200 K. Samples were by 20 MeV W ions at room to peak damage level 0.5 dpa. then annealed desired 1 h and exposed atom beam with flux 144 populate remaining defects. An unannealed sample also used as a reference. Nuclear reaction analysis technique depth profile thermal desorption performed same samples measure amount total retained D. Scanning transmission electron...

10.1088/0031-8949/t167/1/014031 article EN Physica Scripta 2016-01-13

Polycrystalline tungsten (W) samples were simultaneously irradiated by 10.8 MeV W ions and exposed to 300 eV deuterium (D) at different temperatures ranging from 450 K 1000 K. After simultaneous ion irradiation D exposure the additionally low-energy in order populate all defects created beforehand. The amount of damage was evaluated measuring depth profiles thermal desorption spectra. Results compared with data obtained a sequential experiment where first only afterwards defects. At we...

10.1088/1741-4326/ab2261 article EN Nuclear Fusion 2019-05-17

This article describes the DEMO cryostat, vacuum vessel, and tokamak building as well system configurations to integrate main in-vessel components auxiliary systems developed during Pre-Conceptual Design Phase. The vessel is primary component for radiation shielding containment of tritium other radioactive material. Various required operate plasma are integrated in its ports. together with external magnetic coils located inside even larger cryostat that has function provide a enable...

10.1016/j.fusengdes.2021.112966 article EN cc-by Fusion Engineering and Design 2021-12-14

Abstract Single crystalline tungsten was irradiated by the medium-mass ion Si with 7.5 MeV and high mass-ion W 20.3 up to a calculated peak damage level of 0.04 dpa 0.5 dpa. The obtained dislocation structure zone investigated transmission electron microscopy systematically compared each other. Bright-field kinematical images were taken under four different two-beam diffraction conditions g = −200, 020, −110, 110 close [100] axis. observed depth position is in good agreement SRIM profiles....

10.1088/1741-4326/ac75ff article EN cc-by Nuclear Fusion 2022-06-06

Ferritic steel with compositions 83.0Fe–13.5Cr–2.0Al–0.5Ti (alloy A), 79.0Fe–17.5Cr–2.0Al–0.5Ti B), 75.0Fe–21.5Cr–2.0Al–0.5Ti C) and 71.0Fe–25.5Cr–2.0Al–0.5Ti D) (all in wt%) each a 1.0 wt% nano-Y2O3 dispersion were synthesized by mechanical alloying consolidated pulse plasma sintering at 600, 800 1000°C using 75-MPa uniaxial pressure applied for 5 min 70-kA current 3 Hz frequency. X-ray diffraction, scanning transmission electron microscopy energy disperse spectroscopy techniques have been...

10.1080/14786435.2011.619508 article EN The Philosophical Magazine A Journal of Theoretical Experimental and Applied Physics 2011-11-17
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