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FP7

The integration of TBM systems in ITER

Funded under: FP7-EURATOM

Abstract

Testing of breeding blanket modules (TBMs) is one of the ITER goals foreseen from the very beginning of the ITER Project. Six half port TBMs and associated systems are expected to be tested simultaneously in three available Test Ports. This paper presents an initial assessment of the TBM and ITER interface requirements. Four areas of interface were identified. The first area is the port cell interface area, including components like the port plug frame, backside shield, dummy TBM and corresponding tools needed for the TBM maintenance and replacement. The second area is the hot cell, including the needed additional hardware for the service of TBMs, additional remote handling tools, and additional building space needed for the maintenance of the TBM ancillary equipment and the corresponding testing utilities and tools. The third area is the tokamak cooling water system (TCWS) with the need to accommodate six TBM heat transfer systems, each with a footprint of 57 m{2}. The fourth area of interface is the tritium plant. In all these areas modifications in the current ITER design are needed to accommodate the TMB testing. These changes must be incorporated in the new ITER baseline design which is now under preparation. The latest experiments on JET revealed unexpectedly high sensitivity of plasmas in H-mode of confinement to ripples of the magnetic field. The ferromagnetic test modules can create additional ripples. This new issue of interface between ITER and TBMs is also addressed.

Additional information

Authors: CHUYANOV VA, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);KIM SC, Département de Recherches sur la Fusion Contrôlée, Association Euratom-CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (FR);GIANCARLI LM, CEA Saclay, Gif-sur-Yvette (FR);WONG CPC, General Atomics, San Diego (US)
Bibliographic Reference: An oral paper given at: the Eight International Symposium of Fusion Nuclear Technology - ISFNT-8 SI Organised by: Forschungszentrum Karlsruhe GmbH, Leopoldshafen (DE) Held at: Heidelberg Convention Center, Heidelberg (DE)
Availability: This article can be accessed online by subscribers, and can be ordered online by non-subscribers, at: http://dx.doi.org/10.1016/j.fusengdes.2008.05.029
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