Return To: Session CT - ITER
Prev Page: (CT-3) Characteristics of the H-mode Pedestal and Extrapolation
Next Page: (CT-5) ITER Diagnostics: Design Choices and Solutions

(CT-4) Design Improvements and R&D Achievements for VV and In-vessel Components towards ITER Construction and Implications for the R&D Programme

K. Ioki¹⁾, P. Barabaschi¹⁾, V. Barabash¹⁾, S. Chiocchio¹⁾, W. Daenner²⁾, F. Elio¹⁾, M. Enoeda³⁾, A. Gervash⁴⁾, C. Ibbott¹⁾, L. Jones²⁾, V. Krylov⁴⁾, T. Kuroda³⁾, P. Lorenzetto²⁾, E. Martin¹⁾, I. Mazul⁴⁾, M. Merola²⁾, M. Nakahira³⁾, V. Rozov¹⁾, Yu. Strebkov⁴⁾, S. Suzuki³⁾, V. Tanchuk⁴⁾, R. Tivey¹⁾, Yu. Utin¹⁾, M. Yamada^1)
 
1) ITER IT, ITER Garching JWS, Garching, Germany
²⁾ EFDA-CSU, Garching, Germany
³⁾ JAERI, Naka Establishment, Naka-machi, Naka-gun, Ibaraki-ken, Japan
⁴⁾ NTC Sintez, Efremov Inst., St. Petersburg, Russia

Abstract.  Procurement specifications are now being finalised for ITER components whose construction is lengthy, yet which are needed early, such as the vacuum vessel. Although the basic concept of the vacuum vessel (VV) and in-vessel components of the ITER design has stayed the same as reported at the last conference, there have been several detailed design improvements resulting from efforts to raise reliability, to improve better maintainability and to save money. One of the most important achievements in the VV R&D has been the demonstration of the necessary assembly tolerances. Further development of advanced methods of cutting, welding and NDT for the VV have been continued in order to refine manufacturing and improve cost and technical performance. With regard to the related FW/blanket and divertor designs, the R&D has resulted in the development of suitable technologies. Prototypes of the FW panel, the blanket shield block and the divertor components have been successfully fabricated. This paper reviews the recent progress in the design as procurement nears.

Read the full paper in PDF format.