Development and qualification of a bulk tungsten divertor row for JET

Ph. Mertens, H. Altmann, T. Hirai, V. Philipps, G. Pintsuk, J. Rapp, V. Riccardo, B. Schweer, Inge Uytdenhouwen, U. Samm, Rachid Chaouadi

    Research outputpeer-review


    A bulk tungsten divertor row has been developed in the frame of the ITER-like Wall project at JET. It consists of 96 tiles grouped in 48 modules around the torus. The outer strike point is located on those tiles for most of the ITER-relevant, high triangularity plasmas. High power loads (locally up to 10–20MW/m2) and erosion rates are expected, even a risk of melting, especially with the transients or ELM loads. These are demanding conditions for an inertially cooled design as prescribed. A lamella design has been selected for the tungsten, arranged to control the eddy and halo current flows. The lamellae must also withstand high temperature gradients (2200 to 220°C over 40 mm height), without overheating the supporting carrier (600–700°C maximum). As a consequence of the tungsten emissivity, the radiative cooling drops appreciably in comparison with the current CFC tiles, calling for interleaved plasma scenarios in terms of performance. The compromise between shadowing and power handling is discussed, as well as the consequences for operation. Prototypes have been exposed in TEXTOR and in an electron-beam facility (JUDITH-2) to the nominal power density of 7MW/m2 for 10s and, in addition, to higher loads leading to surface temperatures above 2000°C.
    Original languageEnglish
    Pages (from-to)967-970
    JournalJournal of Nuclear Materials
    StatePublished - Jun 2009
    Event18th International Conference on Plasma-Surface Interactions in Controlled Fusion Device - Toledo
    Duration: 26 May 200830 May 2008

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