Fusion Engineering and Design 85 (2010) 1307–1313 Contents lists available at ScienceDirect Fusion Engineering and Design journal homepage: www.elsevier.com/locate/fusengdes ITER vacuum vessel design and construction K. Ioki a,∗,1 , V. Barabash a,1 , C. Bachmann a,1 , P. Chappuis a,1 , C.H. Choi a,1 , J.-J. Cordier a,1 , B. Giraud a,1 , Y. Gribov a,1 , Ph. Heitzenroeder e,1 , G. Johnson a,1 , L. Jones b,1 , C. Jun a,1 , B.C. Kim c,1 , E. Kuzmin d,1 , D. Loesser e,1 , A. Martin a,1 , J.-M. Martinez a,1 , M. Merola a,1 , H. Pathak f,1 , P. Readman a,1 , M. Sugihara a,1 , A. Terasawa a,1 , Yu. Utin a,1 , X. Wang a,1 , S. Wu a,1 a ITER Organization, 13108 St. Paul lez Durance, France b F4E, c/Josep Pla, n.2, Torres Diagonal Litoral, Edificio B3, E-08019, Barcelona, Spain c NFRI, 52 Yeoeundong Yuseonggu, Daejeon, 305-333, South Korea d NTC “Sintez”, Efremov Inst., 189631 Metallostroy, St. Petersburg, Russia e PPPL (MS#41), Princeton University, PO Box 451, Princeton, NJ 08543 USA f IPR, Near Indira Bridge, Bhat, Gandhinagar 382 428, India article info Article history: Available online 15 July 2010 Keywords: Vacuum vessel ITER Design Construction abstract According to recent design review results, the original reference vacuum vessel (VV) design was selected with a number of modifications including 3D shaping of the outboard inner shell. The VV load conditions were updated based on reviews of the plasma disruption and vertical displacement event (VDE) database. The lower port gussets have been reinforced based on structural analysis results, including non-linear buckling. Design of in-vessel coils for the mitigation of edge localized modes (ELM) and plasma vertical stabilization (VS) has progressed. Design of the in-wall-shielding (IWS) has progressed in details. The detailed layout of ferritic steel plates and borated steel plates is optimized based on the toroidal field ripple analysis. The procurement arrangements (PAs) for the VV including ports and IWS have been prepared or signed. Final design reviews were carried out to check readiness for the PA signature. The procedure for licensing the ITER VV according to the French Order on Nuclear Pressure Equipment (ESPN) has started and conformity assessment is being performed by an Agreed Notified Body (ANB). A VV design description document, VV load specification document, hazard and stress analysis reports and particular material appraisal were submitted according to the guideline and RCC-MR requirements. © 2010 ITER Organization. Published by Elsevier B.V. All rights reserved. 1. Introduction The vacuum vessel (VV) is a key component of the ITER facility, the primary functions of the VV are to provide the first con- finement barrier, withstand postulated accidents without loosing confinement, remove the nuclear heating, and provide a boundary consistent with the generation and maintenance of a high quality vacuum and support in-vessel components and their loads. This paper explains the status of the VV design and preparation for the construction. ∗ Corresponding author. E-mail address: Kimihiro.Ioki@iter.org (K. Ioki). 1 On behalf of the ITER Organization, the ITER Parties. 2. VV design and recent activities 2.1. Basic design The VV remains a double-walled torus-shaped structure of SS 316L(N)-IG (ITER Grade) [1]. The main vessel consists of inner and outer shells, poloidal and toroidal ribs and in-wall shielding. Flex- ible support housings (FSHs) and keys are welded to the vessel shells (as shown in Fig. 1) [2], since the blanket modules are directly supported by the VV, electron beam (EB) welding will be used as much as possible for joints between the inner shell and these struc- tures. The layout of welds on the inner and outer shells is very tight considering accessibility for welding and non-destructive exam- ination requirements defined in the design codes. The triangular support plays an important role in the plasma vertical stability con- trol during minor disruptions, and its position and configuration is optimized based on the plasma vertical stability analysis. Detailed design has been developed for the triangular support considering the fabrication method and the structural integrity. 0920-3796/$ – see front matter © 2010 ITER Organization. Published by Elsevier B.V. All rights reserved. doi:10.1016/j.fusengdes.2010.03.027