Published June 2009 | Version v1
Journal article

Review of design principles for ITER VV remote inspection in magnetic field

  • 1. CEA, LIST, Service de Robotique Interactive, 18 route du Panorama, BP6, Fontenay Aux Roses, F-92265 (France)

Description

Because ITER magnet system has a limited number of mechanical and thermal stress cycles, shut down number of the toroidal field is limited during lifetime of ITER. Any inspection device able to withstand the toroidal field between two plasma shots will enhance the inspection frequency capacity of ITER during operation phase. In addition to the high magnetic field the system should also cope with high temperature, ultra-high vacuum and high radiation, in order to keep the reactor availability high. Radiation, ultra-high vacuum and temperature constraints already addressed by on going R and D activities within Europe-considering the required level of radiation is to date the highest encountered in remote handling, and that facing all these constraints at once is an additional issue to overcome. Whereas, operating remote handling systems in high magnetic field is quite new field of investigation. This paper aims to be a guideline for future designers to help them choose among options the adequate solution for an ITER relevant inspection device. It provides the designer an objective view of the different effects that stem from technical choices and help them deciding whether a technology is relevant or not depending on the task's requirements. We have selected a set of technologies and products available for structural design, actuation, sensing and data transmission in order to design inspection remote handling equipment for ITER in the given constraints. These different solutions are commented with specific considerations and directions to have them fit in the specifications. Different design strategies to cope with magnetic field are then discussed, which imply either insensitive design or using the magnetic field as a potential energy source and as a positioning help. This analysis is the first result of one of the projects in the PREFIT partnership, part of the European Fusion Training Scheme.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2009.02.016

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2009.02.016;
PII
S0920-3796(09)00147-1;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
84
Journal Issue
2-6
Journal Page Range
p. 969-973
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
25. symposium on fusion technology
Acronym
SOFT-25
Dates
15-19 Sep 2008
Place
Rostock (Germany)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
41031264
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; INSPECTION; ITER TOKAMAK; MAGNETIC FIELDS; REMOTE HANDLING EQUIPMENT
Descriptors DEC
CLOSED PLASMA DEVICES; EQUIPMENT; MATERIALS HANDLING EQUIPMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.