Development and qualification of a bulk tungsten divertor row for JET

作者：Mertens Ph^*; Altmann H; Hirai T; Philipps V; Pintsuk G; Rapp J; Riccardo V; Schweer B; Uytdenhouwen I; Samm U

来源：Journal of Nuclear Materials, 2009, 390-91: 967-970.

DOI：10.1016/j.jnucmat.2009.01.253

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 10-20 MW/m(2)) 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 degrees C over 40 mm height), without overheating the supporting carrier (600-700 degrees 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 7 MW/m(2) for 10 s and, in addition, to higher loads leading to surface temperatures above 2000 degrees C.

• 出版日期2009-6-15