A5016572380- Fusion materials and technologies
- Nuclear Materials and Properties
- Advanced materials and composites
- Magnetic confinement fusion research
- Metal and Thin Film Mechanics
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Superconducting Materials and Applications
- High-Temperature Coating Behaviors
- Advanced ceramic materials synthesis
- Nuclear Physics and Applications
- Intermetallics and Advanced Alloy Properties
- Ion-surface interactions and analysis
- Diamond and Carbon-based Materials Research
- Metal Alloys Wear and Properties
- Metallurgical and Alloy Processes
- Particle accelerators and beam dynamics
- Advanced Materials Characterization Techniques
- Powder Metallurgy Techniques and Materials
- High-pressure geophysics and materials
- Thermodynamic and Structural Properties of Metals and Alloys
- Nuclear materials and radiation effects
- Graphite, nuclear technology, radiation studies
- Vacuum and Plasma Arcs
- Microstructure and Mechanical Properties of Steels
Forschungszentrum Jülich
2015-2024
Culham Science Centre
2009-2024
Culham Centre for Fusion Energy
2024
Institute for the Science and Technology of Plasmas
2022
Royal Military Academy
2020
Ernst Ruska Centre
2019
Japan External Trade Organization
2015-2016
Nuclear Research and Consultancy Group
2012
University of Toyama
2011
Max Planck Institute for Plasma Physics
2011
Since the ITER divertor design includes tungsten monoblocks in vertical target where heat loads are maximal, to protect leading edges as well technology R&D for high performance armor-heat sink joint were necessary be implemented. In R&D, availability of was demonstrated by flux test monoblock components. Not systematically but frequently macro-cracks appeared at middle after 20 MW/m2 loading. The initiation such considered due cyclic exposure temperature, ∼2000 °C, creep, recrystallization...
This paper describes the progress of DEMO Design Activities in Europe and particularly work done to address critical design integration issues that affect machine configuration performance, plant concept layout selection system technologies. Work continues be primarily focused on a pulsed baseline reactor concept, but number alternative configurations (e.g., double-null divertor snowflake as well ‘flexi’ operates initially an inductively driven regime, with possibility upgraded long-pulse or...
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...
This paper describes the status of pre-conceptual design activities in Europe to advance technical basis a DEMOnstration Fusion Power Plant (DEMO) come operation around middle this century with main aims demonstrating production few hundred MWs net electricity, feasibility closed-tritium fuel cycle, and maintenance systems capable achieving adequate plant availability. is expected benefit as much possible from ITER experience, terms design, licensing, construction. Emphasis on an integrated...
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 EUROfusion materials research program for DEMO in-vessel components aligns with the European Fusion Roadmap and comprises characterization qualification of baseline EUROFER97, CuCrZr tungsten, advanced structural high heat flux developed risk mitigation, as well optical dielectric functional materials. In support future engineering design activities, focus is primarily to assemble qualified data supply process generate material property handbooks, assessment reports, criteria limits...
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 physical properties of tungsten such as the high melting point 3420°C, strength and thermal conductivity, low expansion erosion rate make this material attractive a plasma facing material. However, manufacturing parts by mechanical machining milling turning is extremely costly time intensive because very hard brittle. Powder Injection Molding (PIM) special process allows mass production components, joining different materials without brazing creation composite prototype materials, an...
The First Mirror Test in Joint European Torus (JET) with the International Thermonuclear Experimental Reactor-like wall was performed polycrystalline molybdenum mirrors. Two major types of experiments were done. Using a reciprocating probe system main chamber, short-term exposure made during 0.3 h plasma operation 71 discharges. impact on reflectivity negligible. In long-term experiment lasting 19 13 X-point plasma, 20 Mo mirrors exposed, including four coated 1 μm-thick Rh layer. Optical...
With the aim of a possible improvement material specification for tungsten, five different tungsten products by companies and production technologies (forging rolling) are subject to materials characterization program. Tungsten produced forging results in an uniaxial elongated grain shape while rolled have plate like which has influence on mechanical properties material. The were investigated with respect following parameters: hardness measurements, microstructural investigations, tensile...
• An ultrafine-grained W-Cr-Y alloy exhibiting Y-rich nano-precipitates was produced W-12Cr-0.5Y exhibits excellent oxidation resistance under accident-like conditions W-10Cr-2Ti2 withstands power loads of 2 MW/m without damage the bulk structure A thermal treatment at 1600°C improves thermo-shock W-10Cr-2Ti Self-passivating tungsten based alloys for first wall armour future fusion reactors are expected to provide a major safety advantage compared pure in case loss coolant accident with...
The study summarizes the experimental results on fusion relevant pure heat load exposures of different tungsten products in electron beam devices JUDITH 1 and 2. Besides steady state loading, up to 106 transient ELM-like pulses were applied. A detailed postmortem analysis reveals a wide complex range thermally-induced surface modifications damages, such as roughening due plastic deformation, cracking, melting parts material surface. Different industrially available with varying thermal...