Plasma facing and high heat flux materials – needs for ITER and beyond

Bolt, H.; Barabash, V.; Federici, G.; Linke, J.; Loarte, A.; Roth, J.; Sato, K. N.

doi:10.1016/s0022-3115(02)01175-3

Cited by 437 publications

(240 citation statements)

References 27 publications

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“…The use of tungsten and tungsten alloys for the helium-cooled divertor and possibly for the protection of the helium-cooled first wall in reactor designs going beyond ITER has been discussed and investigated for several years (see, for example, [1][2][3][4][5][6][7][8]). The structure of the Tungsten and Tungsten Alloys (W&WALLOYS) programme of the EFDA Topical Group on Fusion Materials can be found in [9], which also gives a comprehensive review of activities.…”

Section: Introductionmentioning

confidence: 99%

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Rieth

Dudarev

Vicente³

et al. 2013

Journal of Nuclear Materials

653

281

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Section: Introductionmentioning

confidence: 99%

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Rieth

Dudarev

Vicente³

et al. 2013

Journal of Nuclear Materials

653

281

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“…Tungsten is presently considered as one of the most favorable materials for plasma-facing components in future fusion reactors [1,2]. However, as plasma facing material tungsten will be exposed to high fluxes of tritium, alpha-particles and neutrons which may change the material behavior.…”

Section: Introductionmentioning

confidence: 99%

Molecular dynamics study of grain boundary diffusion of hydrogen in tungsten

et al. 2011

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Abstract. Understanding the influence of the microstructure of tungsten on hydrogen transport is crucial for the use of tungsten as first-wall material in fusion reactors. Here we report results from molecular dynamics and transition state studies on the influence of grain boundaries in tungsten on the transport of hydrogen. An exhaustive mapping of possible minimum activation energy migration trajectories for hydrogen as trace impurity reveals a strongly modified activation energy distribution in the neighborhood of grain boundaries together with an altered connectivity matrix. The results indicate that grain boundaries in polycrystalline tungsten may provide an important transport channel, especially for neutron damaged tungsten.

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“…Even the next step device, ITER [1], follows a conservative approach using beryllium for the main chamber PFCs in order to minimise the risk of high power loss through impurity radiation in the central plasma. In a reactor however, Be will not be a viable solution due to its high erosion yield and high-Z components may have to be used [2]. Experiments with PFCs are performed in the ASDEX Upgrade divertor tokamak to explore the feasibility of using tungsten as plasma facing material.…”

Section: Introductionmentioning

confidence: 99%

Operational conditions in a W-clad tokamak

Neu

Hopf

Kallenbach

et al. 2007

Journal of Nuclear Materials

119

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Key word codes: C0600, T1000, P0500, D0500, F0400Experiments with tungsten plasma facing components (PFCs) are performed in the ASDEX Upgrade divertor tokamak and the area covered by W-PFCs has been increased steadily since 1999 reaching 85% for the 2005/2006 campaign. The configurations chosen are W coatings on graphite and CFC. The different locations are subject to different power loads and erosion yields. This is taken into account by selecting different thicknesses in the W-coating manufactured either by physical vapour deposition or vacuum plasma spraying. Power loads in excess of 15 MW/m 2 can be handled in this way. The experiments on ASDEX Upgrade show that plasma operation is feasible with walls and divertor surfaces mostly covered with tungsten, but also reveal critical issues: Fast particles from plasma heating can play a crucial role in W erosion and particle transport must be kept high enough to overcome high impurity content and to prevent central impurity accumulation.

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Plasma facing and high heat flux materials – needs for ITER and beyond

Cited by 437 publications

References 27 publications

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

Molecular dynamics study of grain boundary diffusion of hydrogen in tungsten

Operational conditions in a W-clad tokamak

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