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AbstractAbstract
[en] During the preparation of the procurement specifications for long lead-time items, several detailed vacuum vessel (VV) design improvements are being pursued, such as elimination of the inboard triangular support, adding a separate interspace between inner and outer shells for independent leak detection of field joints, and revising the VV support system to gain a more comfortable structural performance margin. Improvements to the blanket design are also under investigation, an inter-modular key instead of two prismatic keys and a co-axial inlet outlet cooling connection instead of two parallel pipes. One of the most important achievements in the VV R and D has been demonstration of the necessary assembly tolerances. Further development of cutting, welding and nondestructive tests (NDT) for the VV has been continued, and thermal and hydraulic tests have been performed to simulate the VV cooling conditions. In FW/blanket and divertor, full-scale prototypical mock-ups of the FW panel, the blanket shield block, and the divertor components, have been successfully fabricated. These results make us confident in the validity of our design and give us possibilities of alternate fabrication methods. (author)
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International Atomic Energy Agency, Vienna (Austria); Commissariat a l'Energie Atomique (France); 516 p; ISSN 1562-4153;
; Sep 2003; [8 p.]; 19. IAEA fusion energy conference; Lyon (France); 14-19 Oct 2002; CT--4; ISSN 1562-4153;
; Also available on-line: http://www-pub.iaea.org/MTCD/publications/PDF/csp_019c/START.HTM; and on 1 CD-ROM from IAEA, Sales and Promotion Unit: E-mail: sales.publications@iaea.org; Web site: http://www-pub.iaea.org/MTCD/publications/publications.asp; 10 refs, 14 figs


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