Published October 2011 | Version v1
Journal article

Application of remote handling compatibility on ITER plant

  • 1. Oxford Technologies Ltd, 7 Nuffield way, Abingdon, Oxford (United Kingdom)
  • 2. ITER Organisation, Cadarache (France)

Description

The ITER plant will require fully remote maintenance during its operational life. For this to be effective, safe and efficient the plant will have to be developed in accordance with remote handling (RH) compatibility requirements. A system for ensuring RH compatibility on plant designed for Tokamaks was successfully developed and applied, inter alia, by the authors when working at the JET project. The experience gained in assuring RH compatibility of plant at JET is now being applied to RH relevant ITER plant. The methodologies required to ensure RH compatibility of plant include the standardization of common plant items, standardization of RH features, availability of common guidance on RH best practice and a protocol for design and interface review and approval. The protocol in use at ITER is covered by the ITER Remote Maintenance Management System (IRMMS) defines the processes and utilization of management controls including Plant Definition Forms (PDF), Task Definition Forms (TDFs) and RH Compatibility Assessment Forms (RHCA) and the ITER RH Code of Practice. This paper will describe specific examples where the authors have applied the methodology proven at JET to ensure remote handling compatibility on ITER plant. Examples studied are: ·ELM coils (to be installed in-vessel behind the Blanket Modules) - handling both in-vessel, in Casks and at the Hot Cell as well as fully remote installation and connection (mechanical and electrical) in-vessel. ·Neutral beam systems (in-vessel and in the NB Cell) - beam sources, cesium oven, beam line components (accessed in the NB Cell) and Duct Liner (remotely replaced from in-vessel). ·Divertor (in-vessel) - cooling pipe work and remotely operated electrical connector. The RH compatibility process can significantly affect plant design. This paper should therefore be of interest to all parties who develop ITER plant designs.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2011.03.057

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2011.03.057;
PII
S0920-3796(11)00330-9;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
86
Journal Issue
9-11
Journal Page Range
p. 1989-1992
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
26. symposium on fusion technology
Acronym
SOFT-26
Dates
27 Sep - 1 Oct 2010
Place
Porto (Portugal)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
43068000
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPATIBILITY; ITER TOKAMAK; JET TOKAMAK; MAINTENANCE; REMOTE HANDLING
Descriptors DEC
CLOSED PLASMA DEVICES; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Copyright
Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.