Published November 2005 | Version v1
Journal article

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.