Structural analysis and verification of the ITER TF model coil test conditions
Creators
Description
An FE-model already used during the design of the test assembly consisting of the International Thermonuclear Experimental Reactor (ITER) Toroidal Field Model Coil (TFMC), the EURATOM LCT-coil and the Inter Coil Structure (ICS) was extended to allow for predictions of tests, which will be performed in the TOSKA facility. For the first test step, with the TFMC current loaded alone (single coil test), predictions are given for 80 kA, the design current. Because of some uncertainty in the friction behaviour between winding pack (WP) and coil case, a parameter study was performed describing the limiting cases of the coil behaviour. Since the mechanical sensors could be installed only on the outer coil case surface, the possibility of deriving from this information details of the internal coil behaviour also is discussed
Additional details
Identifiers
- PII
- S0920379601004525;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 58-59
- Journal Issue
- 4
- Journal Page Range
- p. 247-251
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33044360
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- DESIGN; FINITE ELEMENT METHOD; ITER TOKAMAK; MAGNET COILS; PERFORMANCE TESTING; TEST FACILITIES
- Descriptors DEC
- CALCULATION METHODS; CLOSED PLASMA DEVICES; ELECTRIC COILS; ELECTRICAL EQUIPMENT; EQUIPMENT; NUMERICAL SOLUTION; TESTING; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Copyright
- Copyright (c) 2001 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.