Title of article :
Engineering design of the ITER blanket and relevant research and development results
Author/Authors :
Elio، نويسنده , , F and Ioki، نويسنده , , K and Barabaschi، نويسنده , , P and Bruno، نويسنده , , L and Cardella، نويسنده , , A and Hechler، نويسنده , , M and Kodama، نويسنده , , T and Lodato، نويسنده , , A and Loesser، نويسنده , , D and Lousteau، نويسنده , , D and Miki، نويسنده , , N and Mohri، نويسنده , , K and Parker، نويسنده , , R and Raffray، نويسنده , , R and Williamson، نويسنده , , D and Yamada، نويسنده , , S and Daenner، نويسنده , , W and Mattas، نويسنده , , R and Strebkov، نويسنده , , Y and Takatsu، نويسنده , , H، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 1999
Pages :
17
From page :
159
To page :
175
Abstract :
The design of the ITER blanket is presented together with the related technology which has been developed. The evolution of this component since the beginning of the EDA is explained in relation to the developing understanding of the thermal deformations and of the electromagnetic forces. These loads lead to a system composed of compact modules protecting a continuous support shell called a backplate. The backplate is a stiff double wall construction which conveys the coolant to the modules. The supports of the module are flexible and allow relative thermal expansions. They are connected and disconnected to the backplate by bolts operated through holes in the front face of the module. The coolant connections and the electrical straps located on the back of the modules are reached similarly. The first wall is integral with the module and cooled in series. A research and development program on materials and joining methods defined the construction path which has been tested in prototypes. The main body is built of stainless steel by forging and drilling or powder hot isostatic pressing (HIP), depending on the complexity of the shape. The first wall includes a dispersion strengthened copper heat sink which is hot isostatic pressed onto the steel body. Beryllium is the basic plasma facing material and is attached by HIP to the copper. Prototypes of the module attachment have been built and are under integrated tests.
Keywords :
Research and Development , ITER blanket
Journal title :
Fusion Engineering and Design
Serial Year :
1999
Journal title :
Fusion Engineering and Design
Record number :
2350649
Link To Document :
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