Published October 2015 | Version v1
Journal article

Development of the ITER Continuous External Rogowski: From conceptual design to final design

  • 1. CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France)
  • 2. ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France)
  • 3. Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain)
  • 4. Ecole polytechnique fédérale de Lausanne, Centre de Recherches en Physique des Plasmas, 1015 Lausanne (Switzerland)
  • 5. Consorzio RFX, C.so Stati Uniti 4, 35127 Padova (Italy)

Description

Highlights: • ITER Continuous External Rogowskis are designed for plasma current measurement. • CER are located in the casing of Toroidal Field Coils and will operate at 4.5 K. • The design of the sensors has been completed and validated through prototypes. • Detailed assembly procedure inside the toroidal field coil casing has been defined. • The CER has passed all the ITER and F4E design review procedures. - Abstract: In ITER, an accurate measurement of plasma current, with high reliability, is mandatory as this parameter is used to demonstrate licensing compliance with regulatory limits. For that purpose, several independent measurements based on magnetic diagnostics have been proposed. Rogowski coils are standard inductive sensors for current measurement in many applications. In ITER, three continuous external Rogowski coils are to be installed in the casing of the toroidal field coils. These sensors are remarkable from several points of view: overall length is about 40 m, high sensitivity needed, located in the toroidal field coil casing at 4.5 K and complex 3D routing with tight bending radius of 50 mm. Since 2005 an extensive work has been carried out to develop and analyze several design options complying with ITER specifications. Prototypes of a selected continuous external Rogowski design were built and tested successfully in terms of electrical, thermal, mechanical and vacuum characteristics. Finally a detailed assembly procedure inside the toroidal field coil casing has been defined according to the coil manufacturing and assembly constraints.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2015.04.047

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2015.04.047;
PII
S0920-3796(15)00276-8;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
96-97
Journal Page Range
p. 878-881
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
48006512
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DESIGN; ELECTRIC CURRENTS; ITER TOKAMAK; MANUFACTURING; PLASMA; RELIABILITY; ROGOWSKI COIL; SENSITIVITY; SENSORS; SPECIFICATIONS
Descriptors DEC
CLOSED PLASMA DEVICES; CURRENTS; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

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