Published December 2008 | Version v1
Journal article

The integration of TBM systems in ITER

  • 1. ITER IO, Building 519, Cadarache CEA, 13108 St. Paul lez Durance (France)
  • 2. CEA Saclay, DEN/CPT, 91191 Gif-sur-Yvette (France)
  • 3. General Atomics, 13-254, P.O. Box 85608, San Diego, CA 92186-5608 (United States)

Description

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 m2. 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

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2008.05.029

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2008.05.029;
PII
S0920-3796(08)00127-0;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
83
Journal Issue
7-9
Journal Page Range
p. 817-823
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
8. international symposium of fusion nuclear technology
Acronym
ISFNT-8 SI
Dates
30 Sep - 5 Oct 2007
Place
Heidelberg (Germany)

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.