Title of article :
Status of ITER blanket attachment design and related R&D
Author/Authors :
Sadakov، نويسنده , , S. and Khomiakov، نويسنده , , S. and Calcagno، نويسنده , , B. and Chappuis، نويسنده , , Ph. and Dellopoulos، نويسنده , , G. and Kolganov، نويسنده , , V. and Merola، نويسنده , , M. and Poddubnyi، نويسنده , , I. and Raffray، نويسنده , , R. and Raharijaona، نويسنده , , J.J. and Ulrickson، نويسنده , , M. and Zhmakin، نويسنده , , A.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2013
Pages :
5
From page :
1853
To page :
1857
Abstract :
Main function of the ITER blanket system [1–3] is to shield the vacuum vessel (VV) from nuclear radiation and thermal energy coming from the plasma. Blanket system consists of discrete blanket modules (BM). Each BM is composed of a first wall panel and a shield block (SB). The shield block is attached to the VV by means of four flexible supports and three or four shear keys, through key pads. All listed supports do have parts with ceramic electro-insulating coatings necessary to exclude the largest loops of eddy currents and restrict EM loads. Electrical connection of each SB to the VV is through two elastic electrical straps. Cooling water is supplied to each BM by one coaxial water connector. This paper summarizes the recent evolution of the blanket attachment system toward design solutions compatible with design loads and numbers of load cycles, and providing sufficient reliability and durability. This evolution was done in a frame of pre-defined external interfaces. The ongoing supporting R&D is also briefly described.
Keywords :
Electrical straps , ITER , ceramic coating , Blanket attachments , Flexible supports , Key pads
Journal title :
Fusion Engineering and Design
Serial Year :
2013
Journal title :
Fusion Engineering and Design
Record number :
2361647
Link To Document :
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