Title of article :
ITER first wall/shield blanket
Author/Authors :
Ioki، نويسنده , , K. and Barabaschi، نويسنده , , P. and Bruno، نويسنده , , L. and Cardella، نويسنده , , A. and Danner، نويسنده , , W. and Elio، نويسنده , , F. and Hechler، نويسنده , , Mahmoud M. and Kodama، نويسنده , , T. and Lodato، نويسنده , , A. and Loesser، نويسنده , , D. and Lousteau، نويسنده , , D. and Mattas، نويسنده , , R. and Miki، نويسنده , , N. and Mohri، نويسنده , , K. and Parker، نويسنده , , R. and Raffray، نويسنده , , R. and Strebkov، نويسنده , , Y.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 1998
Pages :
8
From page :
585
To page :
592
Abstract :
The blanket system comprises first wall/shield modules which are supported on a structural shell called a Back Plate containing water channels for cooling the modules. A modular design of the first wall/shield was chosen to allow independent maintenance through the horizontal mid-plane ports using in-vessel remote handling equipment. The modules are mechanically attached to the back plate for assembly and maintenance. The first wall/shield modules can be replaced with breeding modules for the EPP. In the first wall (FW) region, the water is contained in 316 LN stainless steel pipes surrounded by a copper heat sink except in high heat flux regions where copper pipes with a stainless steel liner are used in the limiter and baffles. The plasma facing surface of the FW will be beryllium except for the lower region of the baffles, where tungsten is used. Electromagnetic analysis and structural analysis has been performed on the back plate and FW/shield modules during a plasma disruption and for a VDE with toroidally asymmetric halo currents. A major R and D project is being conducted to provide needed input for design of the blanket system and to confirm the fabrication technology.
Journal title :
Fusion Engineering and Design
Serial Year :
1998
Journal title :
Fusion Engineering and Design
Record number :
2364722
Link To Document :
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