Structural changes and distribution of accumulated tritium in the carbon based JET tiles

Pajuste, E.; Ķizāne, Gunta; Coad, J. P.; Vītiņš, A.; Kirillova, Anna V.; Halitovs, M.

doi:10.1016/j.jnucmat.2010.09.045

Cited by 3 publications

(3 citation statements)

References 14 publications

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“…The full combustion method followed by tritium measurements with liquid scintillation can be applied to all combustible materials, such as carbon and metals. This method has been originally developed by Vance et al [27] and has been applied to various JET materials [28,29].…”

Section: Tritium Measurement Methodsmentioning

confidence: 99%

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Tritium in plasma-facing components of JET with the ITER-Like-Wall

et al. 2021

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The ITER-Like-Wall project has been carried out at the Joint European Torus (JET) to test plasma facing materials relevant to ITER. Materials being tested include both bulk metals (Be and W) and coatings. Tritium accumulation mechanisms and release properties depend both on the wall components, their location in the vacuum vessel, conditions of exposure to plasma and to the material itself. In this study, bulk beryllium limiter tiles, plasma-facing beryllium coated Inconel components from the main chamber, bulk tungsten and tungsten coated carbon fibre composite divertor tiles were analysed. A range of methods have been developed and applied in order to obtain a comprehensive overview on tritium retention and behaviour in different materials of plasma facing components (PFCs). Tritium content and chemical state were studied by the means of chemical or electrochemical dissolution methods and thermal desorption spectroscopy. Tritium distribution in the vacuum vessel and factors affecting its accumulation have been assessed and discussed.

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Section: Tritium Measurement Methodsmentioning

confidence: 99%

“…X-ray photoelectron spectrometry [30] has a high resolution (nm), however it is limited only to near surface tritium measurement: 3 μm and 0.3 μm for Be and W, respectively. Method has been applied to the JET vacuum vessel tiles retrieved during ILW shutdowns [29,31].…”

Section: Tritium Measurement Methodsmentioning

confidence: 99%

Tritium in plasma-facing components of JET with the ITER-Like-Wall

et al. 2021

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“…The main purpose of the ILW experiment is to demonstrate the plasma compatibility with the metallic wall and to obtain the reduction of the fuel retention [32] and for that purpose a combination of metallic plasma-facing materials comprising bulk beryllium (Be) or Be coated wall components in the main chamber and a tungsten (W) or W-coated divertor tiles, are currently installed and in operation at JET. Prior to the installation of the W-coated tiles at JET the coatings have been extensively tested in JET with the carbon wall (JET-C) [33].…”

Section: Sample Preparationmentioning

confidence: 99%

Tritium retention measurements by accelerator mass spectrometry and full combustion of W-coated and uncoated CFC tiles from the JET divertor

et al. 2016

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Accelerator mass spectrometry (AMS) and the full combustion method (FCM) followed by liquid scintillation counting were applied to quantitatively determine the tritium retention in the tungsten-coated carbon fibre composites (CFC), in comparison to uncoated CFC tiles from the JET divertor. The tiles were adjacent and exposed to plasma operations between 2007 and 2009. The tritium depth profiles are showing that the tritium retention on the W-coated tile was reduced by a factor of 13.5 in comparison to the uncoated tile whereas the bulk tritium concentration is approximately the same for both tiles.

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