Full Paper
Contents  Return  Previous Page  Next Page  Index


Return To: Session ITERP1 - ITER EDA 1
Prev Page: (ITERP1/26) The ITER Divertor Cassette Project
Next Page: (ITERP1/28) The Divertor Remote Maintenance Project


(ITERP1/27) Remote Handling Demonstration of ITER Blanket Module Replacement

S. Kakudate, M. Nakahira, K. Oka, K. Taguchi, K. Obara, E. Tada, K. Shibanuma1, A. Tesini1, R. Haange1, and D. Maisonnier2

Reactor Structure Laboratory, Tokai-JAERI, Tokai-mura, Ibaraki-ken, Japan
1 ITER Joint Central Team, Naka-machi, Naka-gun, Ibaraki-ken, Japan
2 The NET Team, c/o IPP, Garching 85748, Germany

Abstract.  In ITER, the in-vessel components such as blanket are to be maintained or replaced remotely since they will be activated by 14 MeV neutrons, and a complete exchange of shielding blanket with breeding blanket is foreseen after the Basic Performance Phase. The blanket is segmented into about seven hundred modules to facilitate remote maintainability and allow individual module replacement. For this, the remote handing equipment for blanket maintenance is required to handle a module with a dead weight of about 4 tonne within a positioning accuracy of a few mm under intense gamma radiation. According to the ITER R&D program, a rail-mounted vehicle manipulator system was developed and the basic feasibility of this system was verified through prototype testing. Following this, development of full-scale remote handling equipment has been conducted as one of the ITER Seven R&D Projects aiming at a remote handling demonstration of the ITER blanket. As a result, the Blanket Test Platform (BTP) composed of the full-scale remote handling equipment has been completed and the first integrated performance test in March 1998 has shown that the fabricate remote handling equipment satisfies the main requirements of ITER blanket maintenance.

Read the full paper in PDF format.


IAEA 2001