Kinetics of carbide formation in the molybdenum–tungsten coatings used in the ITER-like Wall

Maier, H.; Rasiński, M.; Toussaint, U. von; Greuner, H.; Böswirth, B.; Balden, M.; Elgeti, S.; Ruset, C.; Matthews, G. F.

doi:10.1088/0031-8949/t167/1/014048

Cited by 9 publications

(9 citation statements)

References 15 publications

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“…935 tiles have been coated (see Figure 2), of 14 different types with embedded diagnostics (Langmuir probes, thermocouples and fiber Bragg grating). Subsequent FIB/SEM analysis of this area confirmed porosity formation at the interfaces [13], along with the carbidisation of the layers (MoC/WC/W2C) [14] as identified by STEM in previous studies [15]. The formation of tungsten carbide is a precursor of the coating delamination.…”

Section: W On Non-actively Cooled Graphite Pfcsupporting

confidence: 71%

Overview of the different processes of tungsten coating implemented into WEST tokamak

Firdaouss

Desgranges

Hernandez

et al. 2017

Fusion Engineering and Design

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The Tore Supra tokamak is being transformed in an x-point divertor fusion device within the frame of the WEST (W-for tungsten-Environment in Steady-state Tokamak) project, launched in support to the ITER tungsten divertor strategy. The WEST project aims at testing W monoblock Plasma Facing Units (PFU) under long plasma discharge, with thermal loads of the same magnitude as those expected for ITER. The others Plasma Facing Components (PFC) will also be modified and coated with W to transform Tore Supra into a fully metallic environment. Different coating techniques have been selected, taking into account the specifications of the various PFC: heat loads, complex geometries (length up to 1m) and different substrates (CuCrZr for actively cooled PFC, graphite and CFC for other components). This paper gives an overview on the different processes used and the associated validation program and concludes on the adequacy of the W coating with the WEST experimental program requirements.

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Section: W On Non-actively Cooled Graphite Pfcsupporting

confidence: 71%

Overview of the different processes of tungsten coating implemented into WEST tokamak

Firdaouss

Desgranges

Hernandez

et al. 2017

Fusion Engineering and Design

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“…This is also confirmed by the observation that all the defects appeared and evolved on an edge or a corner, and not in the centre of the tile. Moreover, the temperature and the number of cycles are too low to allow for the phenomenon of W carbidization with the formation of W 2 C and WC, brittle compounds that are likely to break under thermal loads [8,9,10].…”

Section: Results Of the Hhf Cycling Testmentioning

confidence: 99%

Tungsten coating by ATC plasma spraying on CFC for WEST tokamak

et al. 2017

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In the field of fusion experiments using a tokamak, the plasma facing components (PFC) are the closest object to the hot plasma. Due to the plasma-wall interaction, the material composing the PFC may enter the plasma and disturb the experiments. In the past, the main material for PFC was carbon (CFC, graphite), while the future reactors like ITER will be fully metallic, in particular tungsten. The Tore Supra tokamak has been transformed in an x-point divertor fusion device within the frame of the WEST (W-for tungsten-Environment in Steady-state Tokamak) project in order to have plasma conditions close to those expected in ITER. The PFC other than the divertor has been coated with W to transform Tore Supra into a fully metallic environment. Different coating techniques have been selected for different kind of PFC. This paper gives an overview on the coating process used for the antennae protection limiter, the associated validation program and concludes on the adequacy of the W coating with the WEST experimental program requirements and gives perspectives on the development to be pursued.

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“…This is associated with tiles which did not fully undergo the prescribed heat treatment at the time of production. As is mentioned in [44] there is a known mechanism for failure of the coatings by carbidisation if surface temperatures exceed 1350°C for more than two hours [45]. However, this mechanism has not been identified in the samples analysed so far because the protection limit is below this temperature.…”

Section: Hot Spot On the Partly Delaminated Divertor Tilesmentioning

confidence: 94%

Real-time protection of the JET ITER-like wall based on near infrared imaging diagnostic systems

et al. 2018

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In JET with ITER-like wall (JET-ILW), the first wall was changed to metallic materials (tungsten and beryllium) [1] which require a reliable protection system to avoid damage of the plasma-facing components (PFCs) due to beryllium melting or cracking of tungsten owing to thermal fatigue. To address this issue, a protection system with real time control, based on imaging diagnostics, has been implemented on JET-ILW in 2011.

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Kinetics of carbide formation in the molybdenum–tungsten coatings used in the ITER-like Wall

Cited by 9 publications

References 15 publications

Overview of the different processes of tungsten coating implemented into WEST tokamak

Overview of the different processes of tungsten coating implemented into WEST tokamak

Tungsten coating by ATC plasma spraying on CFC for WEST tokamak

Real-time protection of the JET ITER-like wall based on near infrared imaging diagnostic systems

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