Title of article
ITER shielding blanket
Author/Authors
Strebkov، نويسنده , , Yu and Avsjannikov، نويسنده , , A and Baryshev، نويسنده , , M and Blinov، نويسنده , , Yu and Shatalov، نويسنده , , G and Vasiliev، نويسنده , , A and Chernjagin، نويسنده , , A، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 1995
Pages
9
From page
363
To page
371
Abstract
A reference non-breeding blanket is under development now for the ITER Basic Performance Phase for the purpose of high reliability during the first stage of ITER operation. More severe operation modes are expected in this stage with first wall (FW) local heat loads up to 100–300 W cm−2. Integration of a blanket design with protective and start limiters requires new solutions to achieve high reliability, and possible use of beryllium as a protective material leads to technologies. The rigid shielding blanket concept was developed in Russia to satisfy the above-mentioned requirements. The concept is based on a copper alloy FW, austenitic stainless steel blanket structure, water cooling. Beryllium protection is integrated in the FW design. Fabrication technology and assembly procedure are described in parallel with the equipment used.
Journal title
Fusion Engineering and Design
Serial Year
1995
Journal title
Fusion Engineering and Design
Record number
2363045
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