TY - JOUR
T1 - Development and qualification of a bulk tungsten divertor row for JET
AU - Mertens, Ph.
AU - Altmann, H.
AU - Hirai, T.
AU - Philipps, V.
AU - Pintsuk, G.
AU - Rapp, J.
AU - Riccardo, V.
AU - Schweer, B.
AU - Uytdenhouwen, Inge
AU - Samm, U.
A2 - Chaouadi, Rachid
N1 - Score = 10
PY - 2009/6
Y1 - 2009/6
N2 - 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.
AB - 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.
KW - Fusion
KW - tungsten
KW - ITER-like wall
KW - divertor
KW - JET
UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_98665
UR - http://knowledgecentre.sckcen.be/so2/bibref/5910
U2 - 10.1016/j.jnucmat.2009.01.253
DO - 10.1016/j.jnucmat.2009.01.253
M3 - Article
SN - 0022-3115
VL - 390-391
SP - 967
EP - 970
JO - Journal of Nuclear Materials
JF - Journal of Nuclear Materials
T2 - 18th International Conference on Plasma-Surface Interactions in Controlled Fusion Device
Y2 - 26 May 2008 through 30 May 2008
ER -