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1756509 
Journal Article 
A bulk tungsten tile for JET: Heat flux tests in the MARION facility on the power-handling performance and validation of the thermal model 
Mertens, Ph; Altmann, H; Chaumet, P; Joffrin, E; Knaup, M; Matthews, GF; Neubauer, O; Nicolai, D; Riccardo, V; Tanchuk, V; Thompson, V; Uhlemann, R; Samm, U 
2011 
Yes 
Fusion Engineering and Design
ISSN: 0920-3796 
86 
9-11 
1801-1804 
WOS:000297824000053 
In the frame of the ITER-like Wall (ILW) for the JET
tokamak, a divertor row made of bulk tungsten material has been developed for the position where
the outer strike point is located in most of the foreseen plasma configurations. In the absence
of active cooling, this represents a formidable challenge when one considers the temperature
reached by tungsten (T(W,surf) > 2000 degrees C) and the vertical gradient partial derivative
T/partial derivative z= 5 x 10(4) K/m. As the development is drawing to an end and most
components are in production, actual 1:1 prototypes are exposed to an ion beam with a power
density around 7 MW/m(2) on the plasma-facing surface. Advantage is taken of the flexibility of
the MARION facility to bombard the tungsten stack under shallow angles of incidence (similar to 6
degrees) with a powerful beam of ions and neutrals (> 70 MW/m(2) on axis). The shallow angles are
important, with respect to the toroidal wetted surface, for properly simulating the expected
performance under actual tokamak conditions. The MARION tests have been used to validate for a
few typical cases the thermal calculations that were steadily developed along with the tungsten
tile and, at the same time, to gather information on the actual temperatures of individual
components. The latter is an important factor to a finer estimation of the power handling
capabilities. (C) 2011 EURATUM. Published by Elsevier B.V. All rights reserved. 
Divertor; Tungsten; JET; Plasma-facing components; Power handling