Published January 1, 2009 | Version v1
Miscellaneous

Cold Test Facility for the ITER Central Solenoid Coils

  • 1. Oak Ridge National Laboratory, TN (United States)
  • 2. Florida State University, Tallahassee, FL (United States)

Description

The United States, along with the European Union, Russia, Japan, China. South Korea and India, is a collaborative partner in the design, construction and operation of the ITER International Tokamak which will be located a Cadarache, France. One component of the US in kind contribution to the project is the Central Solenoid System for the tokamak magnet system. The Central Solenoid System is a massive assembly 4.4 meters outside diameter, 18.8 meters high and weighing ∼ 1,000 tons. Operating conditions (not simultaneous) are 45kA and 13 T with a maximum field ramp rate of 1.3 T/s producing a maximum flux swing of 277 V s. This combination of performance parameters make the ITER Central Solenoid one the most challenging magnet system ever built Using CICC provide by Japan, the US will deliver the final CS System by fabricating the magnet from six (6) separate 100 ton coils supported and restrained by an external structure. Part of the US responsibilities in delivering this magnet system to the ITER International Organization is to acceptance test each Central Solenoid Coil separately at operating (4K) temperature. The principal acceptance test objectives are coil leak tightness, insulation integrity and overall coil joint quality. Peak test field and test current are reduced without field contributions from adjacent coils and practical installation considerations. This paper will describe an ITER Central Solenoid Cold Test Facility study undertaken by the National High Magnetic Field Laboratory at Florida State University and the United States ITER Project Office at Oak Ridge, TN.

Availability note (English)

Available from Oak Ridge National Laboratory (ORNL); ITER Program

Additional details

Publishing Information

Imprint Pagination
vp.

Conference

Title
2009 IEEE 23. Symposium on Fusion Engineering - SOFE
Dates
31 May - 5 Jun 2009
Place
San Diego, CA (United States)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
43023927
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONSTRUCTION; DESIGN; INTERNATIONAL ORGANIZATIONS; ITER TOKAMAK; MAGNETIC FIELDS; MAGNETS; PERFORMANCE; SOLENOIDS
Descriptors DEC
CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information

Contract/Grant/Project number
AT5512020; ERATITM; AC05-00OR22725
Funding organization
SC USDOE - Office of Science (United States)