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Albuquerque, NM, United States

Raffray A.R.,ITER Organization | Calcagno B.,ITER Organization | Chappuis P.,ITER Organization | Dellopoulos G.,EU ITER Domestic Agency | And 10 more authors.
2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013

The ITER blanket design process is very challenging due to demanding design and interface requirements and constraints, including high heat fluxes from the plasma, large electromagnetic loads during off-normal events, sufficient contribution to the shielding of the vacuum vessel and superconducting coils, and tight interfacing space constraints with many key components. This paper highlights some of these challenges and the associated solutions developed as part of the final blanket design effort. © 2013 IEEE. Source

Martin A.,ITER Organization | Calcagno B.,ITER Organization | Chappuis Ph.,ITER Organization | Daly E.,ITER Organization | And 19 more authors.
Fusion Engineering and Design

The ITER in-vessel components have experienced a major redesign since the ITER Design Review of 2007. A set of in-vessel vertical stabilization (VS) coils and a set of in-vessel Edge Localized Mode (ELM) control coils have been implemented. The blanket system has been redesigned to include first wall (FW) shaping, to upgrade the FW heat removal capability and to allow for an "in situ" replacement. The blanket manifold system has been redesigned to improve leak detection and localisation. The introduction of a new set of in-vessel coils and the design evolution of the blanket system while the ITER project was entering the procurement phase have proven to be a major engineering challenge. This paper describes the status of the redesign of the in-vessel components and the associated integration issues. © 2013 ITER Organization. Source

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