ITER toroidal field model coil (TFMC). Test and analysis summary report (testing handbook) chapter 3 TOSKA FACILITY
Description
In the frame of a contract between the ITER (International Thermonuclear Experimental Reactor) Director and the European Home Team Director was concluded the extension of the TOSKA facility of the Forschungszentrum Karlsruhe as test bed for the ITER toroidal field model coil (TFMC), one of the 7 large research and development projects of the ITER EDA (Engineering Design Activity). The report describes the work and development, which were performed together with industry to extend the existing components and add new components. In this frame a new 2 kW refrigerator was added to the TOSKA facility including the cold lines to the Helium dewar in the TOSKA experimental area. The measuring and control system as well as data acquisition was renewed according to the state-of-the-art. Two power supplies (30 kA, 50 kA) were switched in parallel across an Al bus bar system and combined with an 80 kA dump circuit. For the test of the TFMC in the background field of the EURATOM LCT coil a new 20 kA power supply was taken into operation with the existing 20 kA discharge circuit. Two forced flow cooled 80 kA current leads for the TFMC were developed. The total lifting capacity for loads in the TOSKA building was increased by an ordered new 80 t crane with a suitable cross head (125 t lifting capacity +5 t net mass) to 130 t for assembling and installation of the test arrangement. Numerous pre-tests and development and adaptation work was required to make the components suitable for application. The 1.8 K test of the EURATOM LCT coil and the test of the W 7-X prototype coil count to these tests as overall pre-tests. (orig.)
Availability note (English)
Available from TIB Hannover: FZKA 5141(6614)Additional details
Publishing Information
- Imprint Pagination
- 160 p.
- ISSN
- 0947-8620
- Report number
- FZKA--6614
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 32046304
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Non-conventional Literature
- Descriptors DEI
- ITER TOKAMAK; MAGNET COILS; PERFORMANCE TESTING; POWER SUPPLIES; TOROIDAL CONFIGURATION
- Descriptors DEC
- ANNULAR SPACE; CLOSED CONFIGURATIONS; CLOSED PLASMA DEVICES; CONFIGURATION; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ELECTRONIC EQUIPMENT; EQUIPMENT; MAGNETIC FIELD CONFIGURATIONS; SPACE; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS