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