Th. Loewenhoff
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View article: Experimental characterization of leading edge cracking on bulk tungsten divertor components during 2017–2019 WEST operation
Experimental characterization of leading edge cracking on bulk tungsten divertor components during 2017–2019 WEST operation Open
International audience
View article: Evolution of pre-damaged ITER grade plasma facing components under WEST plasma exposure: smoothing and tungsten sources
Evolution of pre-damaged ITER grade plasma facing components under WEST plasma exposure: smoothing and tungsten sources Open
The evaluation of the impact of plasma-facing units (PFUs) damage on subsequent plasma operation is an important issue for ITER. This is one of the topic addressed by the operation of dedicated PFUs in WEST. From the start of WEST in 2017,…
View article: Initial experiments to regenerate the surface of plasma-facing components by wire-based laser metal deposition
Initial experiments to regenerate the surface of plasma-facing components by wire-based laser metal deposition Open
Plasma-facing components (PFC) in nuclear fusion reactors are exposed to demanding conditions during operation. The combination of thermal loads, plasma exposure as well as neutron induced damage and activation limits the number of materia…
View article: Neutron irradiation effects on the low cycle thermal fatigue performance of first wall mock-ups
Neutron irradiation effects on the low cycle thermal fatigue performance of first wall mock-ups Open
For the first wall (FW) of ITER, beryllium will be the plasma facing material and has to sustain high thermal, particle and neutron loads. In order to assess the synergistic effects of thermal and neutron loads in total ten Be-armored FW n…
View article: Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms
Testing of ITER-grade plasma facing units in the WEST tokamak: Progress in understanding heat loading and damage mechanisms Open
International audience
View article: Thermal fatigue response of W-EUROFER brazed joints by the application of High Heat Flux loads
Thermal fatigue response of W-EUROFER brazed joints by the application of High Heat Flux loads Open
This work has been carried out within the framework of the EUROfusion Consortium, funded by the European Union via the Euratom Research and Training Programme (Grant Agreement No 101052200 — EUROfusion). Views and opinions expressed are ho…
View article: Progress in the Realization of µ-Brush W for Plasma-Facing Components
Progress in the Realization of µ-Brush W for Plasma-Facing Components Open
During the service life of plasma-facing components, they are exposed to cyclic stationary and transient thermal loads. The former causes thermal fatigue and potentially detachment between the plasma-facing material tungsten and the struct…
View article: Additive manufacturing of high density pure tungsten by electron beam melting
Additive manufacturing of high density pure tungsten by electron beam melting Open
Tungsten is an outstanding material and due to its properties like highest melting point and tensile strength of all natural metals and its high thermal conductivity it is a prime candidate for being used in very harsh environments and for…
View article: Recrystallization-mediated crack initiation in tungsten under simultaneous high-flux hydrogen plasma loads and high-cycle transient heating
Recrystallization-mediated crack initiation in tungsten under simultaneous high-flux hydrogen plasma loads and high-cycle transient heating Open
Tungsten and tungsten-based alloys are the leading material choices for the divertor plasma facing components (PFCs) in future fusion reactors. Recrystallization may occur when they undergo high heat loads, drastically modifying the predes…
View article: Thermographic investigation of the effect of plasma exposure on the surface of a MAST upgrade divertor tile in Magnum-PSI
Thermographic investigation of the effect of plasma exposure on the surface of a MAST upgrade divertor tile in Magnum-PSI Open
One of the issues faced by future fusion devices will be high divertor target heat loads. Alternative divertors can promote detachment, flux expansion and dissipation mechanisms to mitigate these heat loads. They have been investigated in …
View article: Challenges for plasma-facing components in nuclear fusion
Challenges for plasma-facing components in nuclear fusion Open
The interaction processes between the burning plasma and the first wall in a fusion reactor are diverse: the first wall will be exposed to extreme thermal loads of up to several tens of megawatts per square meter during quasistationary ope…
View article: Manufacturing, high heat flux testing and post mortem analyses of a W-PIM mock-up
Manufacturing, high heat flux testing and post mortem analyses of a W-PIM mock-up Open
In the framework of the European material development programme for fusion power plants beyond the international thermonuclear experimental reactor (ITER), tungsten (W) is an attractive candidate as plasma facing material for future fusion…
View article: Μicro-structured tungsten: an advanced plasma-facing material
Μicro-structured tungsten: an advanced plasma-facing material Open
A micro-structuring of the tungsten plasma-facing surface can strongly reduce near surface thermal stresses induced by ELM heat fluxes. This approach has been confirmed by numerical simulations with the help of ANSYS software. For experime…
View article: 16th International Conference on Plasma-Facing Materials and Components for Fusion Applications
16th International Conference on Plasma-Facing Materials and Components for Fusion Applications Open
16th International Conference on Plasma-Facing Materials and Components for Fusion Applications
View article: Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification
Plasma–wall interaction studies within the EUROfusion consortium: progress on plasma-facing components development and qualification Open
The provision of a particle and power exhaust solution which is compatible with first-wall components and edge-plasma conditions is a key area of present-day fusion research and mandatory for a successful operation of ITER and DEMO. The wo…
View article: Material properties and their influence on the behaviour of tungsten as plasma facing material
Material properties and their influence on the behaviour of tungsten as plasma facing material Open
With the aim of a possible improvement of the material specification for tungsten, five different tungsten products by different companies and by different production technologies (forging and rolling) are subject to a materials characteri…
View article: Beryllium layer response to ITER-like ELM plasma pulses in QSPA-Be
Beryllium layer response to ITER-like ELM plasma pulses in QSPA-Be Open
Material migration in ITER is expected to move beryllium (Be) eroded from the first wall primarily to the tungsten (W) divertor region and to magnetically shadowed areas of the wall itself. This paper is concerned with experimental study o…
View article: Transient heat load challenges for plasma-facing materials during long-term operation
Transient heat load challenges for plasma-facing materials during long-term operation Open
The study summarizes the experimental results on fusion relevant pure heat load exposures of different tungsten products in the electron beam devices JUDITH 1 and 2. Besides steady state heat loading, up to 106 transient ELM-like pulses we…
View article: Self-castellation of tungsten monoblock under high heat flux loading and impact of material properties
Self-castellation of tungsten monoblock under high heat flux loading and impact of material properties Open
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 at 20MW/m2. The number of monoblocks w…
View article: Use of tungsten material for the ITER divertor
Use of tungsten material for the ITER divertor Open
Since the ITER divertor design includes tungsten monoblocks in the vertical target where heat loads are maximal, the design to protect leading edges as well as technology R&D for high performance armor-heat sink joint were necessary to be …