Overview of the deuterium inventory campaign in Tore Supra: Operational conditions and particle balance

Pégouriè, B.; Brosset, C.; Tsitrone, E.; Beauté, A.; Brémond, S.; Bucalossi, J.; Carpentier, S.; Corre, Y.; Delchambre, E.; Desgranges, C.; Devynck, P.; Douai, D.; Dunand, G.; Ekedahl, A.; Escarguel, A.; Gauthier, E.; Gunn, J.; Hertout, P.; Hong, Suk–Ho; Kazarian, F.; Kočan, M.; Linez, F.; Marandet, Y.; Martinez, A.; Mayer, M.; Meyer, Olivier; Monier‐Garbet, P.; Moreau, Philippe; Oddon, P.; Pascal, J.-Y.; Rimini, F.; Roth, J.; Saint‐Laurent, F.; Samaille, F.; Vartanian, S.; Arnas, C.; Aréou, E.; Gil, C.; Lasalle, J.; Manenc, L.; Martin, Céline; Richou, M.; Roubin, P.; Sabot, R.

doi:10.1016/j.jnucmat.2009.01.095

Cited by 67 publications

(50 citation statements)

References 7 publications

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“…The proton energy spectrum method was used for depth pro ling of deuterium in samples from the main limiter of the tokamak Tore Supra in the framework of the DITS project [23]. One example is shown in Fig.…”

Section: Deuterium In Carbonmentioning

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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130

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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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Section: Deuterium In Carbonmentioning

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:

Self Cite

130

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“…[38,39,40] • D-retention in refractory metals is low from laboratory experiments and observations in AUG with W films [41,42,43], as illustrated in Fig. 18; however, the high D retention observed in C-Mod with bulk Mo [44] has yet to be understood.…”

Section: Plasma Materials Interactionmentioning

confidence: 99%

“…However, dust investigations have just started, the sources are not well known and the extrapolation to ITER is difficult because of different classes of transients. [45,46] • Conditioning by boronisation or Be evaporation is very efficient and helpful for primary O reduction; however, it is not available for long pulse operation [35,40,47,48] • Liquid metals strongly change the edge plasma parameters and open up larger operational space; however, their application to a reactor is challenging due to temperature limitations from evaporation [49,50].…”

Section: Plasma Materials Interactionmentioning

confidence: 99%

High heat flux components—Readiness to proceed from near term fusion systems to power plants

Raffray¹,

Nygren²,

Whyte³

et al. 2010

Fusion Engineering and Design

120

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A present topic of high interest in magnetic fusion is the "gap" between near-term and longterm concepts for high heat flux components (HHFC), and in particular their application in divertors. This paper focuses on this issue with the aim of characterizing the international status of current HHFC design concepts for ITER and describing the different technologies needed in the designs being developed for fusion power plants. Critical corresponding material and physics aspects are highlighted while evaluating the current readiness level of long-term concepts, identifying the design and R&D gaps, and discussing ways to bridge them.2

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“…Apart from deposition of thick layers on plasma-exposed surfaces [12,13] co-deposition in narrow gaps of castellated structures is a major concern [13][14][15][16]. Especially the side walls of gaps are expected to be the main deposition areas [12][13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

“…Especially the side walls of gaps are expected to be the main deposition areas [12][13][14][15][16]. Also deposition far away from the first wall in socalled remote locations may contribute significantly to the total fuel build-up (see [2] and references therein).…”

Section: Introductionmentioning

confidence: 99%

Fuel removal from tile gaps with oxygen discharges: reactivity of neutrals

et al. 2009

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Carbon removal in so-called remote areas, where no energetic species can reach the surface, is investigated with low-temperature glow discharges in pure oxygen. Plasma-deposited amorphous hydrogenated carbon thin films are used as a model system for redeposited films. Erosion measurements are performed on flat substrates as well as on two different 3D test structures. One design consists of 19 mm deep gaps with widths ranging from 0.5 to 4 mm to simulate ITER tile gaps. A second design consists of a flat box-like structure where particles can enter only through a narrow slit. Measurements are performed for substrate temperatures ranging from 290 to 580 K. Erosion rates follow an Arrhenius-type dependence on substrate temperature with an effective activation energy of 0.25 eV. While at room temperature the surface loss probability of the dominant eroding species is 50 % it becomes smaller at elevated temperatures. At elevated temperatures the films are not only removed faster but simultaneously erosion penetrates deeper into the gaps.

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Overview of the deuterium inventory campaign in Tore Supra: Operational conditions and particle balance

Cited by 67 publications

References 7 publications

Quantitative depth profiling of deuterium up to very large depths

Quantitative depth profiling of deuterium up to very large depths

High heat flux components—Readiness to proceed from near term fusion systems to power plants

Fuel removal from tile gaps with oxygen discharges: reactivity of neutrals

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