Published November 1, 2016 | Version v1
Journal article

Overview of progress on the European DEMO remote maintenance strategy

  • 1. RACE/UKAEA, Culham Science Centre, Abingdon OX14 3DB, Oxon (United Kingdom)
  • 2. EUROfusion Consortium, PPP&T Department, Boltzmannstraße 2, 85748 Garching (Germany)
  • 3. VTT Technical Research Centre of Finland, PO Box 1000, FI-02044 VTT, Espoo (Finland)
  • 4. KIT Institut für Fördertechnik und Logistiksysteme, Gotthard-Franz-Straße 8, Geb.50.38, 76131 Karlsruhe (Germany)
  • 5. CIEMAT Laboratorio Nacional de Fusión, Edif. 66, Avenida Complutense 40, 28040 Madrid (Spain)
  • 6. IST, Instituto Superior Técnico, Av. Rovisco Pais 1, 1049-001 Lisboa (Portugal)
  • 7. CEA, IRFM, 13108 St Paul lez Durance (France)

Description

Highlights: • The remote maintenance strategy is applicable to the range of tokamak and component options currently under consideration in Europe • The remote maintenance development work is concentrating on the application and limits of the immature technologies that pose the greatest risk to the feasibility of the maintenance strategy • Position control during the handling of the in-vessel components is one of the areas of high risk and a system is being developed and will be tested prior to concept design to demonstrate the feasibility and capability of a system capable of real time incorporation of changing kinematic data provided by a structural simulator running in parallel • In-vessel recovery and rescue and the pipe joining technology form two more of the high risk areas where developments are being concentrated - Abstract: The EU-DEMO remote maintenance strategy must be relevant for a range of in-vessel component design options. The remote maintenance project must provide an understanding of the limits of the strategy and technologies so as to inform the developing plant design of the maintenance constraints. A comprehensive set of maintenance requirements has been produced, in conjunction with the plant designers, against which design options can be assessed. The proposed maintenance solutions are based around a strategy that deploys casks above each of the vertical ports to exchange the blanket segments and at each of the divertor ports to exchange the divertor cassettes. The casks deploy remote handling equipment to open and close the vacuum vessel, remove and re-install pipework, and replace the in-vessel components. A technical design risk assessment has shown that the largest risks are common to all of the proposed solutions and that they are associated with two key issues, first; the ability to handle the large blanket and divertor components to the required positional accuracy with limited viewing and position feedback, and second; to perform rapid and reliable pipe connections, close to the blankets, with demonstrated quality that meets the safety requirements.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2015.12.013

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2015.12.013;
PII
S0920-3796(15)30395-1;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
109-111
Journal Issue
Part B
Journal Page Range
p. 1392-1398
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
12. international symposium on fusion nuclear technology
Acronym
ISFNT-12
Dates
14-18 Sep 2015
Place
Jeju Island (Korea, Republic of)

Optional Information

Copyright
Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.