Published June 2009 | Version v1
Journal article

Contribution to DEMO reactor RH maintenance assessment

  • 1. CEA, LIST, Service de Robotique Interactive 18 route du Panorama, BP6, FONTENAY AUX ROSES, F-92265 (France)
  • 2. EFDA, Boltzmannstrasse 2, 85748 Garching (Germany)

Description

The scope of this paper is a preliminary assessment of the maintenance scheme in support of the European study for the next generation of fusion reactor: DEMO. Despite other fusion machine requiring remote handling maintenance operations, DEMO is supposed to work under steady state operational conditions. Therefore, requirement on the maintenance scheme is stronger. To target a good availability of the machine along machine operation plan, it is necessary to draw an adequate maintenance scheme. Indeed, due to the high fluxes generated by the plasma in the vacuum vessel, the first wall lifetime is limited, so the frequent replacement is necessary. On current fusion experimental machine, as first wall load conditions are less severe, DEMO condition implies high level of requirement on maintenance time. During DEMO lifetime, several full first wall replacements are expected. To provide access to the vacuum vessel machine for first wall removal, preparatory work is required to set the machine to adequate maintenance conditions and to open the machine properly, the same situation at the end of the maintenance period. Shutdown duration for first wall replacement should be as short as possible to reach the availability target of the machine. From this statement, the maintenance duration should not exceed 20% of the total lifetime of the reactor operation. First wall segmentation (i.e. total number of component to replace) has a high impact onto the replacement time. Considering the number of feasible designs for the first wall segmentation, we concentrate remote handling concept assessments one type of segmentation, the one minimizing the numbers of modules to replace . Assumption on Divertor segmentation for these DEMO studies have similarities with Divertor ITER design; therefore ITER design output is relevant . We assume divertor removal performed in shadow time, while removing the other first wall modules.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2008.11.099

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2008.11.099;
PII
S0920-3796(08)00417-1;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
84
Journal Issue
2-6
Journal Page Range
p. 480-484
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
41031163
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FIRST WALL; MAINTENANCE; REMOTE HANDLING; STEADY-STATE CONDITIONS; THERMONUCLEAR REACTORS
Descriptors DEC
THERMONUCLEAR REACTOR WALLS

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.