The Influence of Carbon in the Plasma on Metal Erosion and Redeposition in the DIII-D Divertor

The Influence of Carbon in the Plasma on Metal Erosion and Redeposition in the DIII-D Divertor PDF Author:
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Category :
Languages : en
Pages : 1

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The Influence of Carbon in the Plasma on Metal Erosion and Redeposition in the DIII-D Divertor

The Influence of Carbon in the Plasma on Metal Erosion and Redeposition in the DIII-D Divertor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 1

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Erosion and Deposition of Metals and Carbon in the DIII-D Divertor

Erosion and Deposition of Metals and Carbon in the DIII-D Divertor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 18

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Net erosion rates at the outer strike point of the DIII-D divertor plasma were measured for several materials during quiescent H-mode operation with deuterium plasmas. Materials examined include graphite, beryllium, tungsten, vanadium and molybdenum. For graphite, net erosion rates up to 4 nm/sec were found. Erosion rates for the metals were much smaller than for carbon. Ion fluxes from Langmuir probe measurements were used to predict gross erosion by sputtering. Measured net erosion was much smaller than predicted gross erosion. Transport of metal atoms by the plasma across the divertor surface was also examined. Light atoms were transported farther than heavy atoms as predicted by impurity transport models.

DiMES Studies of Temperature Dependence of Carbon Erosion and Re-Deposition in the DIII-D Divertor

DiMES Studies of Temperature Dependence of Carbon Erosion and Re-Deposition in the DIII-D Divertor PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 20

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A strong effect of a moderately elevated surface temperature on net carbon deposition and deuterium co-deposition in the DIII-D divertor was observed under detached conditions. A DiMES sample with a gap 2 mm wide and 18 mm deep was exposed to lower-single-null (LSN) L-mode plasmas first at room temperature, and then at 200 C. At the elevated temperature, deuterium co-deposition in the gap was reduced by an order of magnitude. At the plasma-facing surface of the heated sample net carbon erosion was measured at a rate of 3 nm/s, whereas without heating net deposition is normally observed under detachment. In a related experiment three sets of molybdenum mirrors recessed 2 cm below the divertor floor were exposed to identical LSN ELMy H-mode discharges. The first set of mirrors exposed at ambient temperature exhibited net carbon deposition at a rate of up to 3.7 nm/s and suffered a significant drop in reflectivity. In contrast, two other mirror sets exposed at elevated temperatures between 90 C and 175 C exhibited virtually no carbon deposition.

Hydrogen and Helium Recycling at Plasma Facing Materials

Hydrogen and Helium Recycling at Plasma Facing Materials PDF Author: Ahmed Hassanein
Publisher: Springer Science & Business Media
ISBN: 9401004447
Category : Technology & Engineering
Languages : en
Pages : 237

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A compendium representing the current state of the art in the modelling, simulation and physics of the interaction of hydrogen and helium with plasma facing materials in fusion reactors. This is the topic that will determine the success of the production of energy by future Tokamak reactors and it is here discussed by the world's experts. Topics covered are recycling of hydrogen isotopes; wall fuelling and wall pumping; active control of hydrogen recycling; hydrogen and helium behaviour in solids and liquid metals; and databases for recycling.

Suppression of Erosion in the DIII-D Divertor with Detached Plasmas

Suppression of Erosion in the DIII-D Divertor with Detached Plasmas PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 16

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The ability to withstand disruptions makes carbon-based materials attractive for use as plasma-facing components in divertors. However, such materials suffer high erosion rates during attached plasma operation which, in high power long pulse machines, would give short component lifetimes and high tritium inventories. The authors present results from recent experiments in DIII-D, in which the Divertor Materials Evaluation System (DiMES) was used to examine erosion and deposition during short exposures to well defined plasma conditions. These studies show that during operation with detached plasmas, produced by gas injection, net erosion is suppressed everywhere in the divertor. Net deposition of carbon with deuterium was observed at the inner and outer strikepoints and in the private-flux region between strikepoints. For these low temperature plasmas (T{sub e}

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 442

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Plasma Material Interactions in Current Tokamaks and Their Implications for Next Step Fusion Reactors

Plasma Material Interactions in Current Tokamaks and Their Implications for Next Step Fusion Reactors PDF Author: Gianfranco Federici
Publisher:
ISBN:
Category : Fusion reactors
Languages : en
Pages : 342

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Nuclear Fusion

Nuclear Fusion PDF Author:
Publisher:
ISBN:
Category : Electronic journals
Languages : en
Pages : 636

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Metals Abstracts

Metals Abstracts PDF Author:
Publisher:
ISBN:
Category : Metallurgy
Languages : en
Pages : 1628

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Divertor Erosion in DIII-D.

Divertor Erosion in DIII-D. PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Net erosion rates of carbon target plates have been measured in situ for the DIII-D lower divertor. The principal method of obtaining this data is the DiMES sample probe. Recent experiments have focused on erosion at the outer strike-point (OSP) of two divertor plasma conditions: attached (T[sub e]> 40 eV) ELMing plasmas, and detached (T[sub e]2 eV) ELMing plasmas. For the attached cases, the erosion rates exceed 10 cm/exposure-year, even with incident heat flux