Growth of redeposited carbon and its impact on isotope retention properties on tungsten in a high flux deuterium plasma

Sze, F. C.; Chousal, L.; Doerner, R.; Luckhardt, S.

doi:10.1016/s0022-3115(98)00636-9

Cited by 22 publications

(26 citation statements)

References 11 publications

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“…[5][6][7][8][9][10][11][12][13][14][15][16] and helium [10][11][12][16][17][18][19][20][21][22][23][24][25][26] implanted into singlecrystalline and polycrystalline tungsten under different experimental conditions. The essential difference between hydrogen and helium bubbles in tungsten is in the depth of the bubbles: Hydrogen bubbles tend to form at depths that are several orders of magnitude times the projected range, whereas helium bubbles often are located at depths close to the projected range, especially for low temperatures, say T ' 300 K. For example, the helium bubble depths-measured using field ion microscopy~FIM!-in Ref.…”

Section: Ia Hydrogen and Helium Bubbles In Tungstenmentioning

confidence: 99%

The Depths of Hydrogen and Helium Bubbles in Tungsten: A Comparison

Henriksson

Nordlund

Krasheninnikov

et al. 2006

Fusion Science and Technology

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Section: Ia Hydrogen and Helium Bubbles In Tungstenmentioning

confidence: 99%

The Depths of Hydrogen and Helium Bubbles in Tungsten: A Comparison

Henriksson

Nordlund

Krasheninnikov

et al. 2006

Fusion Science and Technology

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“…Measurements are also underway to investigate C-containing layers formation on tungsten [41]. When exposed to a plasma containing 1% Cy it was observed that tungsten develops a mixed-material coating during high-temperature exposure (750°C) and remains clean during room-temperature exposures (SOOC).…”

Section: Implantation Experiencementioning

confidence: 99%

In-vessel tritium retention and removal in ITER

Federici

Anderl

Andrew

et al. 1999

Journal of Nuclear Materials

234

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Invited Review Paper -R2 CEI SUN 3 0 O S T ITritium retention inside the vacuum vessel has emerged as a potentially serious constraint in the operation of the International Thermonuclear Experimental Reactor (ITER). In this paper we review recent tokamak and laboratory data on hydrogen, deuterium and tritium retention for materials and conditions which are of direct relevance to the design of ITER. These data, together with significant advances in understanding the underlying physics, provide the basis for modelling predictions of the tritium inventory in ITER.We present the derivation, and discuss the results, of current predictions both in terms of implantation and codeposition rates, and critically discuss their uncertainties and sensitivity to important design and operation parameters such as the plasma edge conditions, the surface temperature, the presence of mixed-materials, etc. These analyses are consistent with recent tokamak findings and show that codeposition of tritium occurs on the divertor surfaces primarily with carbon eroded from a limited area of the divertor near the strike zones. This issue remains an area of serious concern for ITER. The calculated codeposition rates for ITER are relatively high and the in-vessel tritium inventory limit could be reached, under worst assumptions, in approximately a week of continuous operation.We discuss the implications of these estimates on the design, operation and safety of ITER and present a strategy for resolving the issues. We conclude that as long as carbon is used in ITER, the efficient control and removal of the codeposited tritium is essential. There is a critical need to develop and test in-situ cleaning techniques and procedures that are beyond the current experience of present-day tokamaks. We review some of the principal methods that are being investigated and tested, in conjunction with the R&D work still required to extrapolate their applicability to ITER. Finally, unresolved issues are identified and recommendations are made on potential R&D avenues for their resolution.

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“…Studies of carbon re-deposition on polycrystalline tungsten in a controlled carboncontaminated deuterium plasma environment were performed in the linear magnetized plasma facility PISCES-B [23]. Tungsten substrates were exposed to a high ion flux (10 22 m -2 s -1 ) and low energy (≤100 eV/D) deuterium plasma for a total fluence of the order of 10 26 D/m 2 .…”

Section: Introductionmentioning

confidence: 99%