Published November 2005 | Version v1
Journal article

R and D issues to reach operational level for ITER divertor remote handling equipments

  • 1. CEA/LIST/BP6, F-92265 Fontenay aux Roses Cedex (France)

Description

At European level, for many years, many associations have been engaged for R and D work in connection with the development of remote handling (RH) systems for ITER. As ITER construction moves closer, there is a need to look at R and D issues that ITER faces with respect to lessons learned in other fields where hazardous environment requires significant developments in remote technologies as well. The most significant experience within the fusion community took place at Joint European Torus (JET) where remote handling techniques have been developed to a stage that allows in-vessel maintenance work to be carried out fully remotely. JET's RH team developed a methodology and a rational approach that drive their success. French nuclear energy industry has gathered a significant knowledge in the remote handling technology that can be used as guidelines for the development of the future remote handling systems required for ITER. French Nuclear Energy Agency (CEA) has been involved in many situations, where design of new remote handling equipment (RHE) has been required to operate under satisfactory conditions. During decommissioning activities of existing nuclear facilities, remote handling is required in some situation over a broad range. When considering remote operation in future nuclear facilities, design of RH equipment deeply impacts facilities design activities. In order to draw guidelines for the future of ITER and to reach operational level, clear assessment of design life cycle of remote handling equipment appears essential to cope with necessary R and D effort still required

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2005.08.005;
PII
S0920-3796(05)00411-4;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
74
Journal Issue
1-4
Journal Page Range
p. 59-65
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
37106247
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DECOMMISSIONING; DESIGN; DIVERTORS; ITER TOKAMAK; JET TOKAMAK; LIFE CYCLE; MAINTENANCE; NUCLEAR FACILITIES; OPERATION; RECOMMENDATIONS; REMOTE HANDLING; 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) 2005 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.