Assessment of a cooperative maintenance scheme for ITER divertor cooling pipes
- 1. CEA-LIST, Robotics and Interactive Systems Unit, BP6, F-92265 Fontenay aux Roses Cedex 06 (France)
- 2. EFDA CSU Garching, Boltzmannstrasse 2, 85748 Garching (Germany)
- 3. ITER International Team, ITER Naka Joint Work Site, 801-1, Muouyama, Naka-machi, Naka-gun, Iberaki-ken 311-0193 (Japan)
Description
Divertor cassettes will require scheduled maintenance during the lifetime of ITER. Standard maintenance procedures for cassette removal include connection/disconnection operations of the cassette body from the reactor frame. Remote handling (R.H.) means are therefore required to remove the electrical connector and cut/weld the cassette cooling pipes. Evolutions of ITER design focused on a reduction of the divertor cooling pipes from the initial 6 in. straight pipes to 2.5 in. bent pipes. As a consequence of this new definition, the initial maintenance scheme where maintenance is completely performed from the inside of the pipe by one carrier becomes obsolete. A solution based on the cooperative work between a carrier sent into the pipe to perform part of the maintenance operations and an orbital tool positioned by a manipulator mounted on the Cassette Toroidal Mover (CTM) has been devised. A reference working area is defined and used to perform CAD simulations with a manipulator model. Work area accessibility is assessed using a virtual cutting/welding orbital tool
Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2005.06.084;
- PII
- S0920-3796(05)00203-6;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 75-79
- Journal Page Range
- p. 531-535
- ISSN
- 0920-3796
- CODEN
- FEDEEE
Conference
- Title
- 23. symposium of fusion technology
- Acronym
- SOFT 23
- Dates
- 20-24 Sep 2004
- Place
- Venice (Italy)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 37106473
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONNECTORS; CUTTING; DESIGN; DIVERTORS; ITER TOKAMAK; LIFETIME; MAGNETIC FIELD CONFIGURATIONS; MAGNETIC FIELDS; MAINTENANCE; REMOTE HANDLING; SIMULATION; WELDED JOINTS; WELDING
- Descriptors DEC
- CLOSED PLASMA DEVICES; CONDUCTOR DEVICES; ELECTRICAL EQUIPMENT; EQUIPMENT; FABRICATION; JOINING; JOINTS; MACHINING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.