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Naji, M. |
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Motta, Antonella |
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Aletan, Dirar |
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Mohamed, Tarek |
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Ertürk, Emre |
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Taccardi, Nicola |
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Kononenko, Denys |
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Petrov, R. H. | Madrid |
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Alshaaer, Mazen | Brussels |
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Bih, L. |
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Casati, R. |
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Muller, Hermance |
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Kočí, Jan | Prague |
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Šuljagić, Marija |
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Kalteremidou, Kalliopi-Artemi | Brussels |
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Azam, Siraj |
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Ospanova, Alyiya |
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Blanpain, Bart |
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Ali, M. A. |
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Popa, V. |
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Rančić, M. |
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Ollier, Nadège |
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Azevedo, Nuno Monteiro |
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Landes, Michael |
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Rignanese, Gian-Marco |
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Likonen, Jari
in Cooperation with on an Cooperation-Score of 37%
Topics
Publications (19/19 displayed)
- 2022Irradiation Damage Independent Deuterium Retention in WMoTaNbVcitations
- 2022High-fidelity patterning of AlN and ScAlN thin films with wet chemical etchingcitations
- 2022High-fidelity patterning of AlN and ScAlN thin films with wet chemical etchingcitations
- 2020Comparative study of deuterium retention in irradiated Eurofer and Fe–Cr from a new ion implantation materials facilitycitations
- 2020Impact of H-mode plasma operation on predamaged tungsten divertor tiles in ASDEX Upgradecitations
- 2020Impact of H-mode plasma operation on predamaged tungsten divertor tiles in ASDEX Upgradecitations
- 2018Production of ITER-relevant Be-containing laboratory samples for fuel retention investigations
- 2017The emissivity of W coatings deposited on carbon materials for fusion applicationscitations
- 2016Studies of Be migration in the JET tokamak using AMS with 10 Be markercitations
- 2014First results and surface analysis strategy for plasma-facing components after JET operation with the ITER-like wallcitations
- 2014An overview of the comprehensive First Mirror Test in JET with ITER-like wallcitations
- 2012Pulsed laser deposition using diffractively shaped excimer-laser beamscitations
- 2010First Mirrors Test in JET for ITERcitations
- 2010Surface pretreatment of austenitic stainless steel and copper by chemical, plasma electrolytic or CO 2 cryoblasting techniques for sol-gel coatingcitations
- 2008Structural investigation of re-deposited layers in JETcitations
- 2007Tungsten coatings for the JET ITER-like wall projectcitations
- 2007Investigation of tungsten coatings on graphite and CFCcitations
- 2006Photoluminescence and structural properties of GaInNAs/GaAs quantum wells grown by molecular beam epitaxy under different arsenic pressurescitations
- 2001Silicon diffusion in amorphous carbon filmscitations
Places of action
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article
Impact of H-mode plasma operation on predamaged tungsten divertor tiles in ASDEX Upgrade
Abstract
The effect of continued plasma exposure on two divertor target tiles intentionally damaged before installation was studied for ASDEX Upgrade H-mode discharge conditions. On one tile, made of molybdenum alloy (TZM), superficial melt damage was created in the GLADIS high heat flux test facility. To measure the influence of the resulting surface corrugations on erosion, the tile surface was subsequently covered with a 20 nm tungsten marker layer. A second tile, made of tungsten, was pre-damaged by exposure to 2 × 10<sup>5</sup> consecutive ELM-like heat pulses in the electron beam test facility JUDITH, which resulted in formation of an extended crack network. Both tiles were placed at the outer divertor target of ASDEX Upgrade using the DIM-II divertor manipulator and exposed to a series of 15 identical H-mode discharges. The surface state of both tiles was documented pre- and post-exposure using electron scanning microscopy. SEM analysis of the crack network's microscopic structure did not reveal any additional damage created by plasma exposure but showed deposition of migrated wall materials inside shadowed areas. The erosion pattern of the W-marker layer revealed regions of net erosion as well as of net deposition in the corrugated melt zone. Net erosion up to complete removal of the W marker layer was found at elevated parts of the surface oriented towards the incident plasma flux whereas net deposition was found in corresponding shadowed areas. In contrast, the undamaged surface parts showed a uniform erosion pattern determined by incident plasma ion flux and temperature.