Divertor erosion in DIII-D

Whyte, D.G.; Bastasz, R.; Brooks, J.N.; Wampler, W.R.; West, W.P.; Wong, C.P.C.; Buzhinskij, O.I.; Opimach, I.V.

doi:10.1016/s0022-3115(98)00572-8

Cited by 43 publications

(42 citation statements)

References 23 publications

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“…From the walls it is subsequently eroded and redeposited in the divertor. Small amounts of silicon are visible at the surface due to the siliconization, and oxygen is present at a level of [5][6][7][8][9][10][11][12][13][14][15] The whole inner divertor is a net carbon deposition area. The thickest deposits are observed on tile 4, but tile 5 and a fraction of tile 6B show also thick deposits, although the strike point was never on these tiles.…”

Section: Resultsmentioning

confidence: 99%

“…It was concluded for the DIII-D divertor, that partially detached plasmas have net deposition near the outer strike point, while attached plasmas have net erosion at the outer strike point [10]. However, this conclusion cannot be transferred directly to ASDEX Upgrade due to the different divertor geometry, and a smaller amount of main chamber carbon sources due to increasing coverage with W. …”

Section: Resultsmentioning

confidence: 99%

“…Carbon erosion/deposition was studied in some detail at the TEXTOR limiter [9], and there is some indication about net carbon erosion in the outer divertors of JET and DIII-D [8,10]. This paper presents data about integrated carbon erosion/deposition in the ASDEX Upgrade divertor, based on more than 200 data points measured post mortem with quantitative ion beam analysis methods and SIMS.…”

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confidence: 99%

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Carbon erosion and deposition on the ASDEX Upgrade divertor tiles

Mayer

Rohde

Likonen

et al. 2005

Journal of Nuclear Materials

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Carbon deposition and erosion were measured on ASDEX Upgrade divertor tiles and below the roof baffle during the operation period 2002/2003. The inner divertor is a net carbon deposition area, while a large fraction of the outer divertor is erosion dominated and the roof baffle tiles show a complicated distribution of erosion and deposition areas. In total, 43.7 g B+C were redeposited, of which 88% were deposited on tiles and 9% in remote areas (below roof baffle, on vessel wall structures). 0.6 g C was pumped out as volatile hydrocarbon molecules. Carbon sources in the main chamber are too low by a factor of more than ten to explain the observed carbon divertor deposition. Carbon erosion is observed at the outer divertor strike point tiles, but it is arguable if material can be transported from the outer strike point to the inner divertor.

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Section: Resultsmentioning

confidence: 99%

Section: Resultsmentioning

confidence: 99%

mentioning

confidence: 99%

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Carbon erosion and deposition on the ASDEX Upgrade divertor tiles

Mayer

Rohde

Likonen

et al. 2005

Journal of Nuclear Materials

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“…This, in turn, means a reduced driving potential for diffusion into the bulk; (figure provided by G. [403], activation energy for diffusion E m =0.39 eV [403], binding enthalpy of hydrogen to a vacancy Q t =1.1 eV [400,401], enthalpy of adsorption Q a =0.7 eV [404,405] 39 Net carbon erosion rate at the divertor strike-point vs. strike-point heat flux on JET and DIII-D. JET data [110] and DiMES at 1.5 MW·m −2 [521] were obtained with colorimetry. All other DiMES data come from depthmarked insertable probes [480,530]. The DIII-D long-term results are from net changes in divertor tile height after 9 months of operation [491].…”

Section: Plasma-edge and Plasma-materials Interaction Issues In Next-smentioning

confidence: 99%

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

et al. 2001

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The major increase in discharge duration and plasma energy in a next step DT fusion reactor will give rise to important plasma-material effects that will critically influence its operation, safety and performance. Erosion will increase to a scale of several centimetres from being barely measurable at a micron scale in today's tokamaks. Tritium co-deposited with carbon will strongly affect the operation of machines with carbon plasma facing components. Controlling plasma-wall interactions is critical to achieving high performance in present day tokamaks, and this is likely to continue to be the case in the approach to practical fusion reactors. Recognition of the important consequences of these phenomena stimulated an internationally co-ordinated effort in the field of plasma-surface interactions supporting the Engineering Design Activities of the International Thermonuclear Experimental Reactor project (ITER), and significant progress has been made in better understanding these issues. The paper reviews the underlying physical processes and the existing experimental database of plasma-material interactions both in tokamaks and laboratory simulation facilities for conditions of direct relevance to next step fusion reactors. Two main topical groups of interaction are considered: (i) erosion/redeposition from plasma sputtering and disruptions, including dust and flake generation and (ii) tritium retention and removal. The use of modelling tools to interpret the experimental results and make projections for conditions expected in future devices is explained. Outstanding technical issues and specific recommendations on potential R&D avenues for their resolution are presented.

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“…1 for a schematic representation of the JET divertor). The DIMES probe in DIII-D showed net carbon erosion at the outer strike point under attached plasma conditions [11], and net carbon erosion was also observed in a large fraction of the outer divertor of ASDEX Upgrade [4].…”

Section: Introductionmentioning

confidence: 95%

Tungsten erosion in the outer divertor of JET

Mayer

Likonen²,

Coad³

et al. 2007

Journal of Nuclear Materials

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Erosion of tungsten in the outer JET divertor was determined with a set of tungsten coated divertor tiles during the 2001-2004 discharge campaign. The tungsten marker was strongly eroded, with the largest erosion at the outer strike point position, where more than 75% of the initial W disappeared. Strong erosion is also observed at the outer baffle and horizontal apron of tile 8, where about half of the tungsten has been removed. These numbers are lower boundaries, because the W was locally completely eroded. The tungsten erosion is inhomogeneous on a microscopic level and depends on the micro-topography of the rough surface: large erosion with complete disappearance of the W layer is observed on plasma-facing areas of microscopic ridges, while a smaller erosion and sometimes even deposition of carbon is found on the far side of ridges and in pores.

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Divertor erosion in DIII-D

Cited by 43 publications

References 23 publications

Carbon erosion and deposition on the ASDEX Upgrade divertor tiles

Carbon erosion and deposition on the ASDEX Upgrade divertor tiles

Plasma-material interactions in current tokamaks and their implications for next step fusion reactors

Tungsten erosion in the outer divertor of JET

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