Deuterium retention in carbon fibre composites NB31 and N11 irradiated with low-energy D ions

Roth, J.; Alimov, V.Kh.; Голубева, А. В.; Doerner, R.; Hanna, Jeremy; Tsitrone, E.; Brosset, C.; Rohde, V.; Herrmann, A.; Mayer, M.

doi:10.1016/j.jnucmat.2007.01.164

Cited by 46 publications

(77 citation statements)

References 16 publications

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“…It has been proposed that this di erence may be explained by deep di usion of D into carbon bre composite (CFC) material [32,33]. This deep di usion has been shown experimentally in laboratory experiments [34]. However, while at Tore Supra the whole CIEL limiter is made from CFC and exposes large CFC surfaces to the plasma, the use of CFC is limited to the inner strike point tile 4 in ASDEX Upgrade.…”

Section: Deuterium Inputmentioning

confidence: 99%

The deuterium inventory in ASDEX Upgrade

et al. 2007

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Abstract. The deuterium inventory in ASDEX Upgrade was determined by quantitative ion beam analysis techniques and SIMS for di erent discharge campaigns between the years 2002 and 2005. ASDEX Upgrade was a carbon dominated machine during this phase. Full poloidal sections of the lower and upper divertor tile surfaces, limiter tiles, gaps between divertor tiles, gaps between inner heat shield tiles, and samples from remote areas below the roof ba e and in pump ducts were analyzed, thus o ering an exhaustive survey of all relevant areas in ASDEX Upgrade. Deuterium is mainly trapped on plasma exposed surfaces of inner divertor tiles, where about 70% of the retained deuterium inventory are found. About 20% of the inventory are retained at or below the divertor roof ba e, and about 10% are observed in other areas, such as the outer divertor and in gaps between tiles. The long term deuterium retention is 3 4% of the total deuterium input. The obtained results are compared to gas balance measurements, and conclusions about tritium retention in ITER are made.

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Section: Deuterium Inputmentioning

confidence: 99%

The deuterium inventory in ASDEX Upgrade

et al. 2007

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“…Deuterium can penetrate in these materials up to depths of several tens to several hundreds of µm, where it is trapped at low concentrations [1,2]. It has been assumed that this deep penetration is an important process for the deuterium inventory in the tokamak Tore Supra [3], and it has been shown that deep penetration is dominating the remaining deuterium inventory in the all-tungsten tokamak ASDEX Upgrade [4].…”

Section: Introductionmentioning

confidence: 99%

Quantitative depth profiling of deuterium up to very large depths

Mayer

Gauthier

Sugiyama

et al. 2009

Nuclear Instruments and Methods in Physics Research Section B:

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Quantitative depth pro les of deuterium up to very large depths are achieved from the energy spectra of protons created by the D( 3 He,p)α nuclear reaction at incident energies up to 6 MeV. The advantages of this method compared to the more often applied resonance method are discussed. For light target materials the achievable depth resolution is mainly limited by geometrical spread due to the nite size of the detector aperture, while for heavy materials the resolution is mainly limited by multiple small-angle scattering. A reasonable depth resolution throughout the whole analyzed depth can be obtained by using several di erent incident energies. Depth pro ling up to 38 µm is demonstrated for a-C:D layers deposited on the limiter of Tore Supra, and up to 7.5 µm in tungsten coatings from the divertor of ASDEX Upgrade.

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“…The gas permeability of carbon materials probably explains the observed deep diffusion and deep trapping of deuterium in porous graphite materials [1]: Some hydrocarbon radicals and hydrogen molecules can penetrate deep into the material along the open porosity and then adsorb at the walls of the pore. …”

Section: Resultsmentioning

confidence: 99%

“…A deep diffusion of hydrogen into CFC was observed in laboratory experiments [1], and this deep diffusion and trapping inside the material might be responsible for the high D inventory observed in Tore Supra [2], where large areas of CFC material are exposed to the plasma at the CIEL limiter. The mechanism of deep tritium permeation in carbon-based materials is thought to be migration through open porosity.…”

Section: Introductionmentioning

confidence: 90%

Gas-driven hydrogen isotopes permeation through different carbon materials

Спицын

Голубева

Mayer

et al. 2009

Journal of Nuclear Materials

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Hydrogen gas driven permeation through the fine-grain graphites MPG-8 and R5710, and through CFC NB31 in two main directions has been investigated for sample thicknesses of 1 -7 mm and pressures from 10 -2 -10 Pa. The gas driven permeation occurs through the carbon-base materials by the hydrogen molecular gas flow through the internal porosity network rather than hydrogen atom diffusion through the graphite lattice. The permeabilities of MPG-8 and Nb31 are of the same order, while the permeability of R5710 is two orders of magnitude less. The specific bulk conductivity is about 5×10

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Deuterium retention in carbon fibre composites NB31 and N11 irradiated with low-energy D ions

Abstract: Plasma facing carbon fibre composites (CFC) are used for Tore Supra (CFC N11 )

Cited by 46 publications

References 16 publications

The deuterium inventory in ASDEX Upgrade

The deuterium inventory in ASDEX Upgrade

Quantitative depth profiling of deuterium up to very large depths

Gas-driven hydrogen isotopes permeation through different carbon materials

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