A5041556382- Fusion materials and technologies
- Nuclear Materials and Properties
- Magnetic confinement fusion research
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Advanced materials and composites
- Metal and Thin Film Mechanics
- Nuclear reactor physics and engineering
- Graphite, nuclear technology, radiation studies
- Ion-surface interactions and analysis
- Diamond and Carbon-based Materials Research
- Advanced ceramic materials synthesis
- High-Temperature Coating Behaviors
- Nuclear Physics and Applications
- Metal Alloys Wear and Properties
- Plasma Diagnostics and Applications
- High-pressure geophysics and materials
- High-Velocity Impact and Material Behavior
- Advanced Materials Characterization Techniques
- Intermetallics and Advanced Alloy Properties
- Particle accelerators and beam dynamics
- Vacuum and Plasma Arcs
- Aluminum Alloys Composites Properties
- Microstructure and mechanical properties
- Microstructure and Mechanical Properties of Steels
Forschungszentrum Jülich
2011-2022
Japan External Trade Organization
2015-2016
KTH Royal Institute of Technology
2013
Instituto Superior Técnico
2012
Culham Science Centre
2009
Fusion for Energy
2009
Ghent University
2007
Humboldt-Universität zu Berlin
2003
Max Planck Society
2000-2001
Stadtwerke Jülich (Germany)
1987-1993
The interaction processes between the burning plasma and first wall in a fusion reactor are diverse: will be exposed to extreme thermal loads of up several tens megawatts per square meter during quasistationary operation, combined with repeated intense shocks (with energy densities megajoules pulse durations on millisecond time scale). In addition these loads, subjected bombardment by ions neutral particles (D, T, He) energetic neutrons energies 14 MeV. Hopefully, ITER not only demonstrate...
As part of the ITER Design Review and in response to issues identified by Science Technology Advisory Committee, physics requirements were reviewed as appropriate updated. The focus this paper will be on recent work affecting design with special emphasis topics near-term procurement arrangements. This describe results on: sensitivity studies, poloidal field coil requirements, vertical stability, effect toroidal ripple thermal confinement, material choice heat load for plasma-facing...
Plasma facing components in future thermonuclear fusion devices will be subjected to intense transient thermal loads due type I edge localized modes (ELMs), plasma disruptions, etc. To exclude irreversible damage the divertor targets, local energy deposition must remain below threshold for selected wall materials. For monolithic tungsten (pure and alloys) power densities above ≈0.3 GW m −2 with 1 ms duration result formation of a dense crack network. Thin coatings so-called ITER-like JET,...
DEMO is the name for first stage prototype fusion reactor considered to be next step after ITER towards realizing fusion.For realization of energy especially materials questions pose a significant challenge already today.Heat, particle and neutron loads are problem material lifetime when extrapolating DEMO.For many issues faced advanced solution under discussion or development.In particular components such as wall divertor can benefit from introducing new approaches composites alloys into...
Mitigation of embrittlement caused by recrystallization and radiation is the key issue tungsten (W) based materials for use in advanced nuclear system such as fusion reactor applications. In this paper, our nanostructured W development performed so far to solve reviewed, including new original data. Firstly, basic concept mitigation shown. The approach has yielded ultra-fine grained, recrystallized (UFGR) W(0.251.5)mass%TiC compacts containing fine TiC dispersoids (precipitates). UFGR...
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...
With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907–12), the Tore Supra facility and team expertise (Dumont Plasma Phys. Control. 56 075020) is used to pave way towards ITER divertor procurement operation. It consists implementing a configuration installing ITER-like actively cooled tungsten monoblocks tokamak, taking full benefit of its unique long-pulse capability. user platform, open all partners. This paper describes physics basis WEST:...
Component development for operation in a large-scale fusion device requires thorough testing and qualification the intended operational conditions. In particular environments are necessary which comparable to real conditions, allowing at same time situ/in vacuo diagnostics flexible operation, even beyond design limits during testing. Various electron neutral particle devices provide capabilities high heat load tests, suited material samples components from lab-scale dimensions up full-size...
Cracking thresholds and crack patterns in tungsten targets after repetitive ITER-like edge localized mode (ELM) pulses have been studied recent simulation experiments by laser irradiation. The specimens were tested under selected conditions to quantify the thermal shock response. A Nd:YAG capable of delivering up 32 J energy per pulse with a duration 1 ms at fundamental wavelength λ = 1064 nm has used irradiate ITER-grade samples heat loads. exposures performed for room temperature (RT) as...
The electron beam device JUDITH 1 was used to establish a testing procedure for the qualification of tungsten as plasma facing material. Absorbed power densities 0.19 and 0.38 GW m−2 an edge localized mode-like pulse duration ms were chosen. Furthermore, base temperatures room temperature, 400 °C 1000 allow investigating thermal shock performance in brittle, ductile high temperature regime. Finally, applying 100 pulses under all mentioned conditions helps qualifying general damage behaviour...
The thermal shock performances of two new tungsten grades with 1 and 5 wt% tantalum were characterized the electron beam facility JUDITH 1. As a reference material, ultra-high-purity (W-UHP) purity 99.9999 was used. induced crack networks surface modifications analysed by scanning microscope, light microscopy laser profilometry. Damage cracking thresholds defined for all materials as function absorbed power density base temperature. showed significantly different behaviour, which is, among...
The influence of recrystallization on thermal shock resistance has been identified as an issue that may the long term performance ITER tungsten (W) divertor components. To investigate this a unique series experiments performed W monoblock mock-ups in three EU high heat flux facilities: GLADIS (neutral beam), JUDITH 2 (electron beam) and Magnum-PSI (plasma beam). simulate mitigated edge localised modes, fluxes between 0.11 0.6 GW m−2 were applied for Δt < 1 ms. Two different base...
In the full-tungsten divertor qualification program at ITER Organization, macro-cracks, so called self-castellation were found in a fraction of tungsten monoblocks during cyclic high heat flux loading 20MW/m2. The number with macro-cracks varied products used as armour material. order to understand correlation between macro-crack appearance and W properties, an activity characterize monoblock materials was launched IO. outcome highlighted that higher recrystallization resistance, lower...