Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation

Grisolia, Christian; Counsell, G.; Dinescu, Gheorghe; Semerok, A.; Bekris, N.; Coad, P.; Hopf, C.; Roth, J.; Rubel, M.; Widdowson, A.; Tsitrone, E.; Contributors, Jet

doi:10.1016/j.fusengdes.2007.05.047

Cited by 29 publications

(14 citation statements)

References 32 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…To avoid continuous build-up of a fuel inventory inside the vacuum vessel, a variety of techniques for regular tritium removal have been proposed. These techniques include glow discharge cleaning [4][5][6][7][8], thermal oxidation [9] and laser and flash lamp ablation techniques [10]. Among these techniques, oxygen glow discharge cleaning was proven as one promising candidate to remove re-deposited layers.…”

Section: Introductionmentioning

confidence: 99%

Erosion of tungsten-doped amorphous carbon films in oxygen plasma

Wang

Jacob

Balden

et al. 2012

Journal of Nuclear Materials

View full text Add to dashboard Cite

Abstract:Tungsten-doped amorphous carbon films with 0-9 at.% W concentration were produced by magnetron sputtering and eroded in oxygen plasmas applying different bias voltages and substrate temperatures. The partial C and W erosion rates were determined from the C and W areal density changes measured by Rutherford backscattering spectrometry (RBS). The initial C removal rate increases with increasing ion energy and temperature and decreases with increasing W concentration. For W-doped films the erosion rate decreases with increasing plasma exposure duration. At low bias voltages the erosion process stops after W accumulation at the surface, which protects the carbon underneath from further erosion. RBS and X-ray photoelectron spectroscopy suggest that the Wrich layer at the surface is carbon free and consists of porous WO 3 . Biasing to 200 V leads to removal of W by physical sputtering and, therefore, inhibits the formation of the protecting W oxide layer and the C erosion proceeds.

show abstract

Section: Introductionmentioning

confidence: 99%

Erosion of tungsten-doped amorphous carbon films in oxygen plasma

Wang

Jacob

Balden

et al. 2012

Journal of Nuclear Materials

View full text Add to dashboard Cite

show abstract

“…The formation and accumulation of dust may have a serious impact on the economy and safety in operation of a reactor-class device [3,[10][11][12][13]. The primary concern is related to consequences of oxygen and/or water contact with hot dust in the case of air and/or water leak during the plasma operation giving a high risk of pressure rise and explosion.…”

Section: Introductionmentioning

confidence: 99%

“…The impact of levitation of charged tritiated dust on plasma performance has also been addressed [14]. As a consequence, there are administrative and safety limits for dust content in the ITER vessel [10][11][12]. Access to the reactor in-vessel components will be extremely limited.…”

Section: Introductionmentioning

confidence: 99%

Survey of dust formed in the TEXTOR tokamak: structure and fuel retention

et al. 2009

View full text Add to dashboard Cite

A detailed survey of erosion and deposition on plasma-facing components was performed in the TEXTOR tokamak. Co-deposits and dust particles were collected from graphite limiters and from several locations on the Inconel liner. The total amount of dust (loose material), originating mainly from carbon-rich co-deposits detached from the limiters and the liner, was around 2 g, with sizes from 0.1 µm to 1 mm. The morphology and fuel retention was determined using microscopy methods, ion beam analysis and thermal desorption spectrometry. The study revealed differences in structure and fuel content between deposits from the toroidal and main poloidal limiters. There were also splashes, up to 1 mm in diameter, of molten metal (mainly nickel) on the toroidal limiters. Issues of the dust conversion factor (erosion-to-dust) are addressed and a comparison with results of previous dust surveys at TEXTOR is also briefly presented.

show abstract

“…The analysis is crucial to answer questions: what has happened and why has it happened? This, in turn, enhances understanding of co-deposition in tokamaks and creates grounds for developing tools and methods for fuel removal [73][74][75][76][77].…”

Section: Discussionmentioning

confidence: 99%

Analysis of fuel retention in plasma-facing components from controlled fusion devices

Rubel

Coad

Likonen

et al. 2009

Nuclear Instruments and Methods in Physics Research Section B:

Self Cite

View full text Add to dashboard Cite

a b s t r a c tFirst wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma-wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.

show abstract

Treatment of ITER plasma facing components: Current status and remaining open issues before ITER implementation

Cited by 29 publications

References 32 publications

Erosion of tungsten-doped amorphous carbon films in oxygen plasma

Erosion of tungsten-doped amorphous carbon films in oxygen plasma

Survey of dust formed in the TEXTOR tokamak: structure and fuel retention

Analysis of fuel retention in plasma-facing components from controlled fusion devices

Contact Info

Product

Resources

About