European achievements for ITER high heat flux components

Merola, M.; Vieider, G.; Bet, M.; Vastra, I. Bobin; Briottet, Laurent; Chappuis, P.; Cheyne, K; Dell’Orco, G.; Duglue, D.; Duwe, R.; Erskine, S; Escourbiac, F.; Febvre, M; Grattarola, M.; Moreschi, F; Orsini, A.; Pamato, R; Petrizzi, L.; Plöchl, L; Riccardi, B.; Rigal, Emmanuel; Rödig, M.; Salavy, J.-F.; Schedler, B.; Schlösser, J.; Tähtinen, Seppo; Vesprini, R.; Visca, E.; Wu, C.H.

doi:10.1016/s0920-3796(01)00253-8

Cited by 34 publications

(15 citation statements)

References 4 publications

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“…The capability to manufacture W monoblock high heat flux components by HRP was already assessed in previous ENEA activities and this experimental study confirms that this manufacturing technique can be successful applied to W monoblock components [3,5,7].…”

Section: Discussionsupporting

confidence: 74%

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Manufacturing, testing and post-test examination of ITER divertor vertical target W small scale mock-ups

Visca

Cacciotti

Komarov³

et al. 2011

Fusion Engineering and Design

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Section: Discussionsupporting

confidence: 74%

“…The geometry of the tested mock-up was different from the W mock-ups manufactured under different contracts and tested up to 18-20 MW/m 2 [1][2][3][4][5][6]:…”

Section: Discussionmentioning

confidence: 99%

Manufacturing, testing and post-test examination of ITER divertor vertical target W small scale mock-ups

Visca

Cacciotti

Komarov³

et al. 2011

Fusion Engineering and Design

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“…The current status of R&D on plasma facing materials and components are comprehensively summarized in recent review papers. [5][6][7][8][9] The followings are a brief summary of the currently promising options for ITER PFCs and non-destructive examinations applied during manufacturing.…”

Section: Plasma Facing Materials and Components In Itermentioning

confidence: 99%

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

2005

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The current ITER design employs beryllium, carbon fiber reinforced composite and tungsten as plasma facing materials. Since these materials are exposed to high heat fluxes during the operation, it is essential to perform high heat flux tests for R&D of ITER components. Static heat loads corresponding to cycling loads during normal operation, are estimated to be up to 20 MW/m 2 in the divertor targets and around 0.5 MW/m 2 at the first wall in ITER. For the static high heat flux testing, tests in electron beam facilities, particle beam facilities, IR heater and in-pile tests have been performed. Another type, more critical heat loads, which have high power densities and short durations, corresponding to transient events, i.e. plasma disruption, vertical displacement events (VDEs) and edge localized modes (ELMs) deliver considerable heat flux onto the plasma facing materials. For this purpose, tests in electron beam (short pulses), plasma gun and high power laser facilities have been carried out. The present work summarizes the features of these facilities and recent experimental results as well as the current selection of ITER plasma facing components.

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“…In the present design of the ITER for divertor target strike point zones, the example design consists of 28× 20 mm sized carbon fiber composite (CFC) mono blocks with 46 mm thickness stacked in vertical columns with a 0.5 mm poloidal gap [1]. Therefore hydrocarbons released chemically will migrate to other locations and co-deposit with the fuel isotopes.…”

Section: Introductionmentioning

confidence: 99%

Simulation of Hydrocarbon Redeposition on Plasma Shadowed Areas

Inai

Ohya

2008

Contrib. Plasma Phys.

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In order to investigate tritium co-deposition in the gaps between divertor tiles and the shadowed areas from the step structure of neighboring tiles, a hydrocarbon transport code is combined with castellated structure surface models. The hydrocarbons are easily reflected on the surface and transported in the plasma, with some reaching the gap between the tiles where it is difficult for them to escape, even if they are reflected at the side surfaces. The tile surface is inclined to vary the shadowed area. At a high plasma temperature with increasing inclination angle, the co-deposition in the gap is strongly suppressed whereas most hydrocarbons are deposited on the shadowed area of the tile, which gradually increases. Consequently, there is an inclination angle for which the co-deposition is minimized. Furthermore the net redeposition rate of hydrocarbons released from the tile surface in the gaps is estimated for different gap widths and tile areas.

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European achievements for ITER high heat flux components

Cited by 34 publications

References 4 publications

Manufacturing, testing and post-test examination of ITER divertor vertical target W small scale mock-ups

Manufacturing, testing and post-test examination of ITER divertor vertical target W small scale mock-ups

ITER Relevant High Heat Flux Testing on Plasma Facing Surfaces

Simulation of Hydrocarbon Redeposition on Plasma Shadowed Areas

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