Refine your search:     
Report No.
 - 
Search Results: Records 1-13 displayed on this page of 13
  • 1

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Fabrication process qualification of TF Insert Coil using real ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

IEEE Transactions on Applied Superconductivity, 25(3), p.4200804_1 - 4200804_4, 2015/06

 Times Cited Count:0 Percentile:0(Engineering, Electrical & Electronic)

Journal Articles

Test results of ITER conductors in the SULTAN facility

Bruzzone, P.*; Stepanov, B.*; Wesche, R.*; Mitchell, N.*; Devred, A.*; Nunoya, Yoshihiko; Tronza, V.*; Kim, K.*; Boutboul, T.*; Martovetsky, N.*; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

Starting March 2007, over 60 ITER cable-in-conduit conductors (CICC) have been tested in the SULTAN test facility, Switzerland. For the NbTi CICC, the results confirm the prediction from the strand data, which are made taking the peak field over the conductor cross section as operating field. All the NbTi samples passed the supplier qualification phase. For the Nb$$_{3}$$Sn CICC, the performance prediction is not straightforward because of the irreversible degradation caused by filament damage occurring during cyclic loading. At the first run of the test campaign, the performance of all the Nb$$_{3}$$Sn samples largely meets the target for all the tested samples. Contrary to the NbTi CICC case, the n-index of the transition is substantially lower than in the strands, providing evidence of irreversible degradation. The performance loss upon load cycles and thermal cycles has a broad range among the various conductor samples.

Journal Articles

ITER magnet systems; From qualification to full scale construction

Nakajima, Hideo; Hemmi, Tsutomu; Iguchi, Masahide; Nabara, Yoshihiro; Matsui, Kunihiro; Chida, Yutaka; Kajitani, Hideki; Takano, Katsutoshi; Isono, Takaaki; Koizumi, Norikiyo; et al.

Proceedings of 24th IAEA Fusion Energy Conference (FEC 2012) (CD-ROM), 8 Pages, 2013/03

The ITER organization and 6 Domestic Agencies (DA) have been implementing the construction of ITER superconducting magnet systems. Four DAs have already started full scale construction of Toroidal Field (TF) coil conductors. The qualification of the radial plate manufacture has been completed, and JA and EU are ready for full scale construction. JA has qualified full manufacturing processes of the winding pack with a 1/3 prototype and made 2 full scale mock-ups of the basic segments of TF coil structure to optimize and industrialize the manufacturing process. Preparation and qualification of the full scale construction of the TF coil winding is underway by EU. Procurement of the manufacturing equipment is near completion and qualification of manufacturing processes has already started. The constructions of other components of the ITER magnet systems are also going well towards the main goal of the first plasma in 2020.

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:40.45(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.

Journal Articles

Predictive analysis of the ITER poloidal field conductor insert (PFCI) test program

Zanino, R.*; Astrov, M.*; Bagnasco, M.*; Baker, W.*; Bellina, F.*; Ciazynski, D.*; Egorov, S. A.*; Kim, K.*; Kvitkovic, J. L.*; Lacroix, B.*; et al.

IEEE Transactions on Applied Superconductivity, 17(2), p.1353 - 1357, 2007/06

 Times Cited Count:4 Percentile:30.54(Engineering, Electrical & Electronic)

The PFCI will be tested at JAEA Naka, inside the bore of the ITER Central Solenoid Model Coil. The main test program are the DC characterization of the conductor, the measurement of AC losses in conductor, the hydraulic characterization, the stability and the quench propagation, and the effects of cycling electromagnetic load. Based on and in support of this test program, an extensive campaign of predictive analysis has been initiated on a subset of the above-mentioned test program items and the results of the comparison of selected predictions from different laboratories will be presented and discussed. A sudden quench at 5.7-6.2 K and 45 kA is predicted. The computed temperature increase at the winding outlet is about 0.5 K for the pulse. These results will be compared with the experiment and used for an accurate prediction of the PF coil performance.

Journal Articles

Implications of NbTi short-sample test results and analysis for the ITER Poloidal Field Conductor Insert (PFCI)

Zanino, R.*; Bagnasco, M.*; Baker, W.*; Bellina, F.*; Bruzzone, P.*; della Corte, A.*; Ilyin, Y.*; Martovetsky, N.*; Mitchell, N.*; Muzzi, L.*; et al.

IEEE Transactions on Applied Superconductivity, 16(2), p.886 - 889, 2006/06

 Times Cited Count:7 Percentile:42.11(Engineering, Electrical & Electronic)

As the test of the PFCI is foreseen at JAERI Naka, Japan, it is essential to consider in detail the lessons learned from the short NbTi sample tests, as well as the issues left open after them, in order to develop a suitable test program of the PFCI aimed at bridging the extrapolation gap between measured strand and future PF coil performance. Here we consider in particular the following issues: (1) the actual possibility to quench the PFCI conductor in the TCS tests before quenching the intermediate joint, (2) the question of the so-called sudden or premature quench, based on SULTAN sample results, applying a recently developed multi-solid and multi-channel extension of the Mithrandir code to a short sample analysis; (3) the feasibility of the AC losses calorimetry in the PFCI. These results show that Tcs measurement and the calorimetric measurement of AC losses will be carried out successfully. However, we need further analytic works for the problem of the sudden quench.

Journal Articles

Acoustic emission and disturbances in central solenoid model coil for international thermonuclear experimental reactor

Arai, K.*; Ninomiya, Akira*; Ishigooka, Takeshi*; Takano, Katsutoshi*; Nakajima, Hideo; Michael, P.*; Vieira, R.*; Martovetsky, N.*; Sborchia, C.*; Alekseev, A.*; et al.

Cryogenics, 44(1), p.15 - 27, 2004/01

 Times Cited Count:3 Percentile:16.14(Thermodynamics)

no abstracts in English

Journal Articles

Pulsed operation test results of the ITER-CS model coil and CS insert

Ando, Toshinari*; Isono, Takaaki; Kato, Takashi; Koizumi, Norikiyo; Okuno, Kiyoshi; Matsui, Kunihiro; Martovetsky, N.*; Nunoya, Yoshihiko; Ricci, M.*; Takahashi, Yoshikazu; et al.

IEEE Transactions on Applied Superconductivity, 12(1), p.496 - 499, 2002/03

 Times Cited Count:5 Percentile:35.87(Engineering, Electrical & Electronic)

no abstracts in English

Journal Articles

First test results for the ITER central solenoid model coil

Kato, Takashi; Tsuji, Hiroshi; Ando, Toshinari; Takahashi, Yoshikazu; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Koizumi, Norikiyo; Kawano, Katsumi; Oshikiri, Masayuki*; et al.

Fusion Engineering and Design, 56-57, p.59 - 70, 2001/10

 Times Cited Count:17 Percentile:76.5(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Acoustic emission in ITER CS model coil and CS insert coil

Ninomiya, Akira*; Arai, Kazuaki*; Takano, Katsutoshi*; Nakajima, Hideo; Michael, P.*; Martovetsky, N.*; Takahashi, Yoshikazu; Kato, Takashi; Ishigooka, Takeshi*; Kaiho, Katsuyuki*; et al.

Teion Kogaku, 36(6), p.344 - 353, 2001/06

no abstracts in English

Journal Articles

Progress of the ITER central solenoid model coil programme

Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.

Nuclear Fusion, 41(5), p.645 - 651, 2001/05

 Times Cited Count:55 Percentile:84.47(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

AC loss performance of the 100kwh SMES model coil

Hamajima, Takataro*; Hanai, Satoshi*; Wachi, Yoshihiro*; Shimada, Mamoru*; Ono, Michitaka*; Martovetsky, N.*; Zbasnik, J.*; Moller, J.*; Takahashi, Yoshikazu; Matsui, Kunihiro; et al.

IEEE Transactions on Applied Superconductivity, 10(1), p.812 - 815, 2000/03

 Times Cited Count:10 Percentile:54.49(Engineering, Electrical & Electronic)

no abstracts in English

Oral presentation

Fabrication of insert coil with ITER TF conductor

Ozeki, Hidemasa; Isono, Takaaki; Kawano, Katsumi; Saito, Toru; Kawasaki, Tsutomu; Nishino, Katsumi; Okuno, Kiyoshi; Kido, Shuichi*; Semba, Tomoyuki*; Suzuki, Yozo*; et al.

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
  • 1