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Journal Articles

Benchmarking of mechanical test facilities related to ITER CICC steel jackets

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:11 Percentile:42.25(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.

Journal Articles

Preparation for the ITER central solenoid conductor manufacturing

Hamada, Kazuya; Nunoya, Yoshihiko; Isono, Takaaki; Takahashi, Yoshikazu; Kawano, Katsumi; Saito, Toru; Oshikiri, Masayuki; Uno, Yasuhiro; Koizumi, Norikiyo; Nakajima, Hideo; et al.

IEEE Transactions on Applied Superconductivity, 22(3), p.4203404_1 - 4203404_4, 2012/06

 Times Cited Count:14 Percentile:35.23(Engineering, Electrical & Electronic)

Japan Atomic Energy Agency (JAEA) has the responsibility for procurement of all of the ITER central solenoid (CS) conductor lengths. The CS conductor is composed of 576 Nb$$_{3}$$ Sn superconducting strands and 288 Cu strands assembled together into a multistage cable and protected by a circle-in-square sheath tube (jacket) with the outer dimension of 49 mm. In preparation for CS conductor production, the following R&D activities have been performed; (1) Mechanical tests at 4 K have been performed for jacket candidate materials such as 316LN and JK2LB, (2) Welding test for filler selection, (3) Measurement of coefficient of sliding friction using a 100-m long dummy cable, (4) Deformation characteristics of the conductor cross section after compaction and spooling. As a result of these R&D, the CS conductor jacket manufacturing technologies have been confirmed to start the procurement of the CS conductor.

Journal Articles

Strain and magnetic-field characterization of a bronze-route Nb$$_3$$Sn ITER wire; Benchmarking of strain measurement facilities at NIST and University of Twente

Cheggour, N.*; Nijhuis, A.*; Krooshoop, H. J. G.*; Lu, X. F.*; Splett, J.*; Stauffer, T. C.*; Goodrich, L. F.*; Jewell, M. C.*; Devred, A.*; Nabara, Yoshihiro

IEEE Transactions on Applied Superconductivity, 22(3), p.4805104_1 - 4805104_4, 2012/06

 Times Cited Count:10 Percentile:44.38(Engineering, Electrical & Electronic)

A benchmarking experiment was conducted to compare strain measurement facilities at the National Institute of Standards and Technology (NIST) and the University of Twente. The critical current of a bronze-route Nb$$_3$$Sn ITER wire was measured as a function of axial strain and magnetic field in liquid helium temperature at both institutes. NIST used a Walters' spring strain device and University of Twente used a Pacman apparatus. The ITER bronze-route wire investigated had a very high irreversible strain limit and allowed the comparison of data over a wide range of applied strain from $$-1%$$ to $$+1%$$. A full account of the data analysis and comparisons will be presented. Measurement protocols and parameterization procedures will also be discussed.

Journal Articles

Status of ITER conductor development and production

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:106 Percentile:2.5(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$$_3$$Sn strands while the PF and CC conductors need around 250 tons of NbTi strands. The required amount of Nb$$_3$$Sn 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.

Journal Articles

Addressing the technical challenges for the construction of the ITER Central Solenoid

Libeyre, P.*; Bessette, D.*; Jewell, M.*; Jong, C.*; Lyraud, C.*; Rodriguez-Mateos, M.*; Hamada, Kazuya; Reiersen, W.*; Martovetsky, N.*; Rey, C.*; et al.

IEEE Transactions on Applied Superconductivity, 22(3), p.4201104_1 - 4201104_4, 2012/06

 Times Cited Count:6 Percentile:57.71(Engineering, Electrical & Electronic)

The Central Solenoid (CS) of the ITER magnet system will play a major role in tokamak operation, providing not only the major part of the inductive flux variation required to drive the plasma but also contributing to the shaping of the field lines and to vertical stability control. To meet these requirements, the design has been optimised by splitting the CS into six independently powered coils enclosed inside an external structure which provides vertical precompression thus preventing separation of the coils and, additionally, acting as a support to net resulting loads. To ensure that the CS design meets the ITER criteria, several analyses are performed along with a series of R&D trials to qualify the technologies to be used for the manufacture of the conductor, the coils and the structure.

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