C. Ruset

ORCID: 0000-0002-7348-3686
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About
Contact & Profiles
Research Areas
  • Fusion materials and technologies
  • Metal and Thin Film Mechanics
  • Nuclear Materials and Properties
  • Diamond and Carbon-based Materials Research
  • Magnetic confinement fusion research
  • Advanced materials and composites
  • Superconducting Materials and Applications
  • Ion-surface interactions and analysis
  • Laser-Plasma Interactions and Diagnostics
  • Nuclear Physics and Applications
  • Nuclear reactor physics and engineering
  • High-Temperature Coating Behaviors
  • Laser-induced spectroscopy and plasma
  • Plasma Applications and Diagnostics
  • Copper Interconnects and Reliability
  • Plasma Diagnostics and Applications
  • Cold Fusion and Nuclear Reactions
  • GaN-based semiconductor devices and materials
  • Particle accelerators and beam dynamics
  • Boron and Carbon Nanomaterials Research
  • Semiconductor materials and devices
  • Metallurgical Processes and Thermodynamics
  • X-ray Spectroscopy and Fluorescence Analysis
  • Electrohydrodynamics and Fluid Dynamics
  • Erosion and Abrasive Machining

National Institute for Laser Plasma and Radiation Physics
2013-2024

Max Planck Society
2016

Max Planck Institute for Plasma Physics
2016

KTH Royal Institute of Technology
2013

Warsaw University of Technology
2010-2012

CEA Cadarache
2011

Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2011

Culham Science Centre
2009-2011

Forschungszentrum Jülich
2006-2007

National Research and Development Institute on Occupational Safety
2007

Work is in progress to completely replace, 2008/9, the existing JET CFC tiles with a configuration of plasma facing materials consistent ITER design. The ITER-like wall (ILW) will be created combination beryllium (Be), tungsten (W), W-coated and Be-coated inconel tiles, material depending on local anticipated heat flux geometry. It part an integrated package enhancements whose aim develop understanding issues techniques required operate inductive advanced scenarios as close possible...

10.1088/0031-8949/2007/t128/027 article EN Physica Scripta 2007-03-01

Erosion and deposition were studied in the JET divertor during first ITER-like wall campaign 2011 to 2012 using marker tiles. An almost complete poloidal section consisting of tiles 0, 1, 3, 4, 6, 7, 8 was studied. The data from tile surfaces completed by analysis samples remote areas inner cladding. total mass material deposited decreased a factor 4–9 compared carbon all-carbon operation before 2010. Deposits consist mainly beryllium with 5–20 at.% oxygen, respectively, small amounts Ni,...

10.1088/0031-8949/t167/1/014051 article EN Physica Scripta 2016-01-21

Combined magnetron sputtering and ion implantation (CMSII) is a deposition technique involving simultaneous high energy bombardment of the coating during its growth. A voltage pulse discharge (U=40 kV, τ=20 μs, f=25 Hz) superposed over in this way, positive ions are accelerated to components be coated, bombarding initially substrate then itself. In framework ITER-like wall project method was applied produce nanostructured W coatings on carbon fibre composite (CFC) substrate. These have been...

10.1088/0031-8949/2007/t128/033 article EN Physica Scripta 2007-03-01

This paper presents an overview of the status and relevant technical issues for ITER-like Wall Project with emphasis on progress since 11th International Workshop Plasma-Facing Materials Components Fusion Applications.

10.1088/0031-8949/2009/t138/014030 article EN Physica Scripta 2009-12-01

Erosion of plasma-facing materials and successive transport redeposition eroded material are crucial processes determining the lifetime components trapped tritium inventory in redeposited layers. deposition JET divertor were studied during second ITER-like wall campaign ILW-2 2013–2014 by using a poloidal row specially prepared marker tiles including tungsten bulk tile 5. The analyzed elastic backscattering with 3–4.5 MeV incident protons nuclear reaction analysis 0.8–4.5 3He ions before...

10.1088/1402-4896/aa8ff9 article EN Physica Scripta 2017-11-23

The manuscript presents an overview of the erosion and deposition data in inner outer JET divertor observed during first three ITER-like wall campaigns (JET-ILW1, JET-ILW2, JET-ILW3). Erosion were studied using core samples cut out from tiles. For a similar general pattern was all campaigns: More than 60% total occurred upper region on tiles 0 1, where Be transported deposited scrape-off layer. High only tile 5. In JET-ILW2 3, together with high power fluxes at bottom 7. Additionally, peaks...

10.1088/1402-4896/ab5c11 article EN Physica Scripta 2020-01-01

In the frame of JET's ITER-like wall (ILW) project tungsten coatings on carbon fibre reinforced substrates will be used in divertor and highly loaded areas main chamber. Fourteen different types samples were produced by physical or chemical vapour deposition vacuum plasma spray (VPS) with coating thickness 4, 10 200 μm. Similarly, three VPS W (200 μm) two graphite substrates, for use at strike-point regions ASDEX Upgrade. All subjected to thermal screening cycling tests ion beam facility...

10.1088/0031-8949/2007/t128/029 article EN Physica Scripta 2007-03-01

The chosen materials for plasma facing components the deuterium/tritium phase of ITER are beryllium and tungsten. These have already been widely investigated in various devices like ion beam or electron tests. However, operation this material combination a large tokamak including wall interaction, degradation, erosion mixing has not proven yet.The ITER-like Wall, which recently installed JET, consists bulk tungsten coated CFC divertor tiles as well INCONEL main chamber. experiments JET will...

10.13182/fst12-a14103 article EN Fusion Science & Technology 2012-08-01

The ITER-like wall (ILW) at JET provides a unique opportunity to study the combination of material (beryllium and tungsten) that will be used for plasma facing components (PFCs) in ITER. Both limiters (Be) divertor (CFC W coated bulk W) have been designed maximize their power handling capability. During last experimental campaign (October 2010–July 2011) this capability has assessed even challenged case Be wall. limiters' (19 MW m−2 s−1/2), predicted with simple model, proven robust by...

10.1088/0031-8949/2014/t159/014009 article EN Physica Scripta 2014-04-01

The net erosion and deposition pattern of carbon from the Test Divertor Unit (TDU) stellarator W7-X was determined. Special target elements with marker layers consisting about 300 nm molybdenum 5–10 μm on top were used during operational phase OP 1.2a. thicknesses determined by elastic backscattering spectrometry (EBS) using 2.5 MeV protons before after plasma exposure laser-induced breakdown spectroscopy selected exposure. Scanning electron microscopy for investigating surface morphology...

10.1088/1402-4896/ab4b8c article EN Physica Scripta 2020-01-01

For the ITER-like wall project at JET present main chamber CFC tiles will be exchanged with Be and in parallel a fully tungsten-clad divertor prepared. Therefore three R&D programmes were initiated: coatings on Inconel as well erosion markers developed for first of chamber. High heat flux screening cyclic loading tests carried out showed excellent performance, above required power energy density. conceptual design bulk W horizontal target plate was investigated, emphasis minimizing...

10.1088/0029-5515/47/3/009 article EN Nuclear Fusion 2007-02-28

ITER foresees applying laser induced breakdown spectroscopy (LIBS) as a tool for quantitative assessment of fuel retention in the first walls. One open problem related to LIBS application is choice type. Here we compare two Nd/YAG lasers with different pulse durations, 0.15 and 8 ns, working at λ = 1064 nm studies samples D-doped W/Al coatings ≈ 3 μm thickness (Al used proxy Be) on Mo. Low pressure argon was background gas. Experiments were done conditions where other factors (broadening...

10.1016/j.nme.2018.11.018 article EN cc-by Nuclear Materials and Energy 2018-11-30
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