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Vostner, A.*; Pong, I.*; Bessette, D.*; Devred, A.*; Sgobba, S.*; Jung, A.*; Weiss, K.-P.*; Jewell, M. C.*; Liu, S.*; Yu, W.*; et al.
IEEE Transactions on Applied Superconductivity, 23(3), p.9500705_1 - 9500705_5, 2013/06
Times Cited Count：12 Percentile：53.02(Engineering, Electrical & Electronic)The ITER Cable-In-Conduit Conductor (CICC) used in the superconducting magnet system consists of a cable made of 300 to 1440 strands housed in a stainless steel tube (a.k.a. jacket or conduit). There are circular, square, as well as circle-in-square jackets, made of either a very low carbon AISI 316LN grade stainless steel or a high Mn austenitic stainless steel developed for ITER called JK2LB. Selected mechanical properties of the base material and weld joint were tested at room temperature and/or cryogenic temperatures (
7 K). The Domestic Agencies (DAs) reference laboratories and the ITER-IO appointed reference laboratories, CERN and Karlsruhe Institute of Technology (KIT) performed mechanical tests. This paper will compare the test results (e.g. elongation to failure) from different laboratories.
Devred, A.*; Backbier, I.*; Bessette, D.*; Bevillard, G.*; Gardner, M.*; Jewell, M.*; Mitchell, N.*; Pong, I.*; Vostner, A.*
IEEE Transactions on Applied Superconductivity, 22(3), p.4804909_1 - 4804909_9, 2012/06
Times Cited Count：132 Percentile：96.91(Engineering, Electrical & Electronic)The ITER magnet system is made up of 4 sets of coils: 18 Toroidal Field (TF) coils, 6 Poloidal Field (PF) coils, 6 Central Solenoid (CS) coils and 9 pairs of Correction Coils (CC's). All of them are wound from Cable-In-Conduit Conductors (CICC's) made up of superconducting and copper strands assembled into a multistage, rope-type cable inserted into a conduit of butt-welded austenitic steel tubes. The TF and CS conductors call for about 500 tons of Nb
Sn strands while the PF and CC conductors need around 250 tons of NbTi strands. The required amount of NbSn strands far exceeds pre-existing industrial capacity and calls for a significant worldwide production scale up. After recalling the technical requirements defined by the ITER Internal Organization (IO), we detail the in-kind procurement sharing of the various conductor types among the 6 ITER Domestic Agencies (DA's) involved: China, Europe, Japan, South Korea, Russia, and the United States, and we present a status of ongoing productions. The most advanced production is that for the TF coils, where all 6 DAs have qualified suppliers and have already registered more than 30% of the expected production data into the web-based ITER Conductor Database developed by the IO.
Schaffer, M. J.*; Snipes, J. A.*; Gohil, P.*; de Vries, P.*; Evans, T. E.*; Fenstermacher, M. E.*; Gao, X.*; Garofalo, A. M.*; Gates, D. A.*; Greenfield, C. M.*; et al.
Nuclear Fusion, 51(10), p.103028_1 - 103028_11, 2011/10
Times Cited Count：35 Percentile：80.59(Physics, Fluids & Plasmas)Experiments at DIII-D investigated the effects of ferromagnetic error fields similar to those expected from proposed ITER Test Blanket Modules (TBMs). Studied were effects on: plasma rotation and locking; confinement; L-H transition; edge localized mode (ELM) suppression by resonant magnetic perturbations; ELMs and the H-mode pedestal; energetic particle losses; and more. The experiments used a 3-coil mock-up of 2 magnetized ITER TBMs in one ITER equatorial port. The experiments did not reveal any effect likely to preclude ITER operations with a TBM-like error field. The largest effect was slowed plasma toroidal rotation v across the entire radial profile by as much as 
via non-resonant braking. Changes to global 
, 
and 
were 
3 times smaller. These effects are stronger at higher 
and lower 
. Other effects were smaller.
Snipes, J. A.*; Schaffer, M. J.*; Gohil, P.*; de Vries, P.*; Fenstermacher, M. E.*; Evans, T. E.*; Gao, X. M.*; Garofalo, A.*; Gates, D. A.*; Greenfield, C. M.*; et al.
no journal, ,
A series of experiments was performed on DIII-D to mock-up the field that will be induced in a pair of ferromagnetic Test Blanket Modules (TBMs) in ITER to determine the effects of such error fields on plasma operation and performance. A set of coils producing both poloidal and toroidal fields was placed inside a re-entrant horizontal port close to the plasma. The coils produce a localized ripple due to the toroidal field (TF) + TBM up to 5.7%, which is more than four times that expected from a pair of representative 1.3 ton TBMs in ITER. The experiments show that the reduction in the toroidal rotation is sensitive to the ripple. On the other hand, the confinement is reduced by up to 15-18% for local ripple 
3% but is hardly affected at 1.7% local ripple.
