Carbon erosion and deposition on the ASDEX Upgrade divertor tiles

Mayer, M.; Rohde, V.; Likonen, J.; Vainonen-Ahlgren, E.; Krieger, K.; Gong, Xuzhong; Chen, J.

doi:10.1016/j.jnucmat.2004.10.046

Cited by 37 publications

(47 citation statements)

References 19 publications

(35 reference statements)

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“…The lowest few cm of tile 1 (close to the corner with tile 10) show a small deposition area. This small deposition area was already observed in the carbon deposition pattern in the carbon dominated machine [2].…”

Section: Net Tungsten Erosion and Redepositionsupporting

confidence: 71%

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

et al. 2009

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Net erosion and deposition of tungsten in the ASDEX Upgrade divertor were determined after the 2007 campaign by using thin tungsten marker stripes. ASDEX Upgrade had full-tungsten plasmafacing components during this campaign. The inner divertor and the roof baffle were net W deposition areas with a maximum deposition of about 1×10 18 W-atoms/cm 2 in the private flux region below the inner strike point. Net erosion of W was observed in the whole outer divertor, with the largest erosion close to the outer strike point. Only a small fraction of the tungsten eroded in the main chamber and in the outer divertor was found in redeposits in the inner divertor, while a large fraction was either redeposited at unidentified places in the main chamber or has formed dust.

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Section: Net Tungsten Erosion and Redepositionsupporting

confidence: 71%

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

et al. 2009

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“…Fuel retention in ASDEX Upgrade is associated with co-deposition of C layers at the divertor with a rate of 3.5 10 20 C/s, which is similar to the JET values [423]. Most of this deposition occurs at the inner divertor with some deposition taking place the outer one too [423,424] and, at present, cannot be explained only in terms of erosion of main wall carbon PFCs [285,424].…”

Section: Database On Fuel Retention In Present Fusion Devicesmentioning

confidence: 68%

“…Most of this deposition occurs at the inner divertor with some deposition taking place the outer one too [423,424] and, at present, cannot be explained only in terms of erosion of main wall carbon PFCs [285,424]. Retention of fuel in remote areas of the divertor, such as pump ducts, is very small in ASDEX Upgrade.…”

Section: Database On Fuel Retention In Present Fusion Devicesmentioning

confidence: 95%

Chapter 4: Power and particle control

Loarte¹,

et al. 2007

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Abstract.Progress, since the ITER Physics Basis publication, in understanding the processes that will determine the properties of the plasma edge and its interaction with material elements in ITER is described. Experimental areas where significant progress has taken place are : energy transport in the SOL in particular of the anomalous transport scaling, particle transport in the SOL that plays a major role in the interaction of diverted plasmas with the main chamber material elements, ELM energy deposition on material elements and the transport mechanism for the ELM energy from the main plasma to the plasma facing components, the physics of plasma detachment and neutral dynamics including the edge density profile structure and the control of plasma particle content and He removal, the erosion of low and high Z materials in fusion devices, their transport to the core plasma and their migration at the plasma edge including the formation of mixed materials, the processes determining the size and location of the retention of tritium in fusion devices and methods to remove it and the processes determining the efficiency of the various fuelling methods as well as their development towards the ITER requirements. This experimental progress has been accompanied by the development of modelling tools for the physical processes at the edge plasma and plasma-materials interaction and the further validation of these models by comparing their predictions with the new experimental results. Progress in the modelling development and validation has been mostly concentrated in the following areas : refinement of the predictions for ITER with plasma edge modelling codes by inclusion of detailed geometrical features of the divertor and the introduction of physical effects, which can play a 2 major role in determining the divertor parameters at the divertor for ITER conditions such as hydrogen radiation transport and neutral-neutral collisions, modelling of the ion orbits at the plasma edge, which can play a role in determining power deposition at the divertor target, models for plasma-materials and plasma dynamics interaction during ELMs and disruptions, models for the transport of impurities at the plasma edge to describe the core contamination by impurities and the migration of eroded materials at the edge plasma and its associated tritium retention and models for the turbulent processes that determine the anomalous transport of energy and particles across the SOL. The implications for the expected performance of the reference regimes in ITER, the operation of the ITER device and the lifetime of the plasma facing materials are discussed. Introduction.This chapter outlines the significant progress achieved since the ITER Physics Basis in understanding basic scrape-off layer (SOL) and divertor processes in a tokamak. The interaction of plasma with first-wall surfaces will have considerable impact on the performance of fusion plasmas, the lifetime of plasma facing components, and the retention of tritium in next step Burning Plasma E...

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“…The tiles were analyzed again after exposure using RBS under the same conditions, thus providing information about the change of the marker layer thickness and material deposition on the marker [10,11]. Deuterium was detected by nuclear reaction analysis (NRA) using the D( 3 He,p) 4 He reaction at dierent incident energies [14].…”

Section: Wall Materialsmentioning

confidence: 99%

Carbon balance and deuterium inventory from a carbon dominated to a full tungsten ASDEX Upgrade

Mayer

Rohde

Sugiyama

et al. 2009

Journal of Nuclear Materials

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The evolution of carbon/boron deposition and the deuterium inventory were determined during the transition from a carbon dominated to a full tungsten ASDEX Upgrade. In the carbon dominated machine about 17 g of carbon were deposited at the inner divertor and in remote areas during one standard discharge campaign. Main carbon sources were the ICRH antennae protection limiters in the main chamber. After coating these limiters with tungsten the carbon deposition decreased to 35 g. The remaining carbon originated mainly from erosion at the outer divertor strike point. Transition to a full tungsten machine resulted in a further decrease of the carbon deposition to about 1 g. 1.31.7 g deuterium was trapped in codeposited carbon/boron layers in the divertor and in remote areas during the carbon dominated campaigns. The deuterium inventory decreased to 0.140.22 g in the full tungsten machine.

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Carbon erosion and deposition on the ASDEX Upgrade divertor tiles

Cited by 37 publications

References 19 publications

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

Chapter 4: Power and particle control

Carbon balance and deuterium inventory from a carbon dominated to a full tungsten ASDEX Upgrade

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