Published October 2015 | Version v1
Journal article

Design and integration of lower ports for ITER diagnostic systems

  • 1. ITER Organization, Route de Vinon-sur-Verdon – CS 90 046 – 13067 St Paul Lez Durance Cedex (France)
  • 2. IOFFE Institute, Saint Petersburg (Russian Federation)
  • 3. Oxford Technologies Ltd., Abingdon (United Kingdom)
  • 4. Russian Federation Domestic Agency, Moscow (Russian Federation)
  • 5. CIEMAT, Madrid (Spain)
  • 6. Japanese Domestic Agency, Naka (Japan)

Description

Highlights: • Lower port structures are in its conceptual design phase. • Electromagnetic and seismic loads, will dominate all other mechanical loads. • Design allows diagnostics support, neutron shielding while and signals transmission. • Installation and maintenance operations are fully remote handling compatible. - Abstract: All around the ITER vacuum vessel, forty-four ports will provide access to the vacuum vessel for remote handling operations, diagnostic systems, heating, and vacuum systems: 18 upper ports, 17 equatorial ports, and 9 lower ports. Among the lower ports, three of them will be used for the remote handling installation of the ITER divertor. Once the divertor is in place, these ports will host various diagnostic systems mounted in the so-called diagnostic racks. The diagnostic racks must allow the support and cooling of the diagnostics, extraction of the required diagnostic signals, and providing access and maintainability while minimizing the leakage of radiation toward the back of the port where the humans are allowed to enter. A fully integrated inner rack, carrying the near plasma diagnostic components, will be an stainless steel structure, 4.2 m long, with a maximum weight of 10 t. This structure brings water for cooling and baking at maximum temperature of 240 °C and provides connection with gas, vacuum and electric services. Additional racks (placed away from plasma and not requiring cooling) may be required for the support of some particular diagnostic components. The diagnostics racks and its associated ex vessel structures, which are in its conceptual design phase, are being designed to survive the lifetime of ITER of 20 years. This paper presents the current state of development including interfaces, diagnostic integration, operation and maintenance, shielding requirements, remote handling, loads cases and discussion of the main challenges coming from the severe environment and engineering requirements.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2015.06.186

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2015.06.186;
PII
S0920-3796(15)30157-5;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
96-97
Journal Page Range
p. 83-88
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
28. symposium on fusion technology
Acronym
SOFT-28
Dates
29 Sep - 3 Oct 2014
Place
San Sebastian (Spain)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
48006345
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINERS; COOLING; DIVERTORS; ITER TOKAMAK; LEAKS; MAINTENANCE; OPERATION; PLASMA DIAGNOSTICS; REMOTE HANDLING; SERVICE LIFE; SHIELDING; STAINLESS STEELS; VACUUM SYSTEMS; WEIGHT
Descriptors DEC
ALLOYS; CARBON ADDITIONS; CLOSED PLASMA DEVICES; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LIFETIME; STEELS; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS; TRANSITION ELEMENT ALLOYS

Optional Information

Copyright
Copyright (c) 2015 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.