The design and development of divertor remote handling equipment for ITER

J. Palmer; M. Irving; Jorma Järvenpää; H. Mäkinen; H. Saarinen; M. Siuko; Arto Timperi; S. Verho

doi:10.1016/j.fusengdes.2007.05.073

The design and development of divertor remote handling equipment for ITER

J. Palmer (Corresponding Author), M. Irving, Jorma Järvenpää, H. Mäkinen, H. Saarinen, M. Siuko, Arto Timperi, S. Verho

VTT Technical Research Centre of Finland

Research output: Contribution to journal › Article › Scientific › peer-review

33 Citations (Scopus)

Abstract

A key ITER maintenance activity is the complete exchange of the divertor system at scheduled intervals, typically after every 3–4 years of plasma operations. ITER divertor replacement is classified as a remote handling (RH) Class 1 activity and as such, detailed design of the associated equipment and verification of its operation before ITER construction by way of prototypes and mock-ups, is considered an essential activity. With this in mind, a major step in the EU RH development programme for ITER involves the construction of a full-scale physical test facility in which to verify and refine divertor RH equipment designs through the operation of prototypes closely replicating those proposed for ITER. This paper reports on the design of one such prototype, namely the cassette multifunctional mover (CMM), and outlines the current build status and planning for the new RH mock-up facility in which to test this device.

Original language	English
Pages (from-to)	1977-1982
Journal	Fusion Engineering and Design
Volume	82
Issue number	15-24
DOIs	https://doi.org/10.1016/j.fusengdes.2007.05.073
Publication status	Published - 2007
MoE publication type	A1 Journal article-refereed

Keywords

ITER
Divertor
Remote handling

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

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10.1016/j.fusengdes.2007.05.073

Cite this

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title = "The design and development of divertor remote handling equipment for ITER",

abstract = "A key ITER maintenance activity is the complete exchange of the divertor system at scheduled intervals, typically after every 3–4 years of plasma operations. ITER divertor replacement is classified as a remote handling (RH) Class 1 activity and as such, detailed design of the associated equipment and verification of its operation before ITER construction by way of prototypes and mock-ups, is considered an essential activity. With this in mind, a major step in the EU RH development programme for ITER involves the construction of a full-scale physical test facility in which to verify and refine divertor RH equipment designs through the operation of prototypes closely replicating those proposed for ITER. This paper reports on the design of one such prototype, namely the cassette multifunctional mover (CMM), and outlines the current build status and planning for the new RH mock-up facility in which to test this device.",

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AU - Palmer, J.

AU - Irving, M.

AU - Järvenpää, Jorma

AU - Mäkinen, H.

AU - Saarinen, H.

AU - Siuko, M.

AU - Timperi, Arto

AU - Verho, S.

PY - 2007

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AB - A key ITER maintenance activity is the complete exchange of the divertor system at scheduled intervals, typically after every 3–4 years of plasma operations. ITER divertor replacement is classified as a remote handling (RH) Class 1 activity and as such, detailed design of the associated equipment and verification of its operation before ITER construction by way of prototypes and mock-ups, is considered an essential activity. With this in mind, a major step in the EU RH development programme for ITER involves the construction of a full-scale physical test facility in which to verify and refine divertor RH equipment designs through the operation of prototypes closely replicating those proposed for ITER. This paper reports on the design of one such prototype, namely the cassette multifunctional mover (CMM), and outlines the current build status and planning for the new RH mock-up facility in which to test this device.

KW - ITER

KW - Divertor

KW - Remote handling

U2 - 10.1016/j.fusengdes.2007.05.073

DO - 10.1016/j.fusengdes.2007.05.073

M3 - Article

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EP - 1982

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

IS - 15-24

ER -

The design and development of divertor remote handling equipment for ITER

Abstract

Keywords

UN SDGs

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