Final steps to an all tungsten divertor tokamak

Neu, R.; Bobkov, V.; Dux, R.; Kallenbach, A.; Pütterich, T.; Greuner, H.; Gruber, O.; Herrmann, A.; Hopf, C.; Krieger, K.; Maggi, C. F.; Maier, H.; Mayer, M.; Rohde, V.; Schmid, K.; Suttrop, W.

doi:10.1016/j.jnucmat.2006.12.021

Cited by 88 publications

(68 citation statements)

References 21 publications

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“…The replacement of carbon tiles by tungsten coated ones started in summer 1999, resulting in a full tungsten machine in the year 2007 [9]. The increasing W coverage is summarized in table 1, a graphical representation can be found in [16, Fig.…”

Section: Wall Materialsmentioning

confidence: 99%

“…1]. The technical solution chosen was of W coatings on graphite and CFC [9]. Most tiles were coated with a 34 µm thick W layer using physical vapor deposition (PVD), the outer strike point tiles were coated with 200 µm W using vacuum plasma spraying (VPS).…”

Section: Wall Materialsmentioning

confidence: 99%

“…The area of W-PFCs was increased steadily from 1999 to 2007, nally reaching a full-W machine [9]. The stepwise transition from a full carbon to a full tungsten machine oered the unique possibility to study the inuence of the wall material on materials migration and deuterium inventory.…”

mentioning

confidence: 99%

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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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Section: Wall Materialsmentioning

confidence: 99%

Section: Wall Materialsmentioning

confidence: 99%

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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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“…This option is tested in ASDEX Upgrade (AUG) by using tungsten for PFCs. A stepwise transition from carbon to tungsten coated carbon tiles was selected to minimize the effort and to study material migration [1], [2], [3].…”

Section: Introductionmentioning

confidence: 99%

Dynamic and static deuterium inventory in ASDEX Upgrade with tungsten first wall

Rohde¹,

Mayer

Mertens

et al. 2009

Nucl. Fusion

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Hydrogen retention in the divertor tokamak ASDEX Upgrade is studied by surface analysis and gas balances methods. Comparing carbon and tungsten plasma facing components (PFCs), the deuterium content of deposits at the divertor plates has dropped by a factor of 13. With tungsten PFCs only 0.7 % of the puffed hydrogen is retained, including a significant amount deep implanted in the tungsten coatings at the outer divertor. Gas balances for ITER relevant high density H-mode discharges leads to a hydrogen retention averaged over a discharge of 8.2 ± 3.3% for tungsten PFCs and 23 ± 7% for carbon PFCs. For tungsten PFCs wall saturation is observed, i.e. only 1.5 ± 3.5% of the puffed gas is retained after reaching steady state conditions. Within the accuracy of the gas balance measurements all hydrogen outgasses within 15 min.

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“…During the last seven years ASDEX Upgrade was converted from a carbon dominated to a full-tungsten machine [12]. The stepwise replacement of carbon by tungsten plasma-facing components offered the unique possibility to identify net carbon and tungsten sources by monitoring changes in the amount of redeposited material [4].…”

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confidence: 99%

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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Final steps to an all tungsten divertor tokamak

Cited by 88 publications

References 21 publications

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

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

Dynamic and static deuterium inventory in ASDEX Upgrade with tungsten first wall

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

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