Title of article :
ITER plasma-facing components
Author/Authors :
Merola، نويسنده , , Mario and Loesser، نويسنده , , D. and Martin، نويسنده , , A. and Chappuis، نويسنده , , P. and Mitteau، نويسنده , , R. and Komarov، نويسنده , , V. and Pitts، نويسنده , , R.A. and Gicquel، نويسنده , , S. and Barabash، نويسنده , , V. and Giancarli، نويسنده , , L. and Palmer، نويسنده , , J. and Nakahira، نويسنده , , M. and Loarte، نويسنده , , A. and Campbell، نويسنده , , D. and Eaton، نويسنده , , R. and Kukushkin، نويسنده , , A، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2010
Pages :
11
From page :
2312
To page :
2322
Abstract :
The ITER plasma-facing components directly face the thermonuclear plasma and include the divertor, the blanket and the test blanket modules with their corresponding frames. vertor is located at the bottom of the plasma chamber and is aimed at exhausting the major part of the plasma thermal power (including alpha power) and at minimising the helium and impurity content in the plasma. anket system provides a physical boundary for the plasma transients and contributes to the thermal and nuclear shielding of the vacuum vessel and external machine components. It consists of modular shielding elements known as blanket modules which are attached to the vacuum vessel. Each blanket module consists of two major components: a plasma-facing first wall panel and a shield block. st blanket modules are mock-ups of DEMO breeding blankets. There are three ITER equatorial ports devoted to test blanket modules, each of them providing for the allocation of two breeding modules inserted in a steel frame and in front of a shield block.
Keywords :
First wall , High heat flux components , Blanket , ITER , Divertor
Journal title :
Fusion Engineering and Design
Serial Year :
2010
Journal title :
Fusion Engineering and Design
Record number :
2357330
Link To Document :
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